ML20236Q985
| ML20236Q985 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/16/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236Q987 | List: |
| References | |
| NUDOCS 8711230009 | |
| Download: ML20236Q985 (16) | |
Text
1 h
'o UNITED STATES.
-8
-g NUCLEAR REGULATORY. COMMISSION o
WASHINGTON, D. C. 20666
~%*****/
1 ALABAMA POWER COMPANY DOCKET N0. 50-348 I
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 74
)
License No. NPF-2
.j Ij 1.
The Nuclear Regulatory Commiss' ion'(the Commission) has found that:
q
'l A.
The application for amendment by Alabama Power Company (the y
licensee), dated May 4, 1987, complies with the' standards and-y 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; 4
B.
The. facility will operate in conformNy with the. application, as amended, the provisions of the Act, and the regulations.of the Commission-l l
C.
There is reasonable assurance: (i) that the activities authorized bv i
l this amendment can be conducted withut endangering the health and i
l safety of the public, and (ii) that such activities will be conducted 4 6 i
in compliance with the Commission's regulations, 1
D.
The issuance of this license amendment will not.be inimical to the j
common defense and security or t; the health and' safety of:the public; and i
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.
l l
l 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:
1 I
8711230009 871116 ADOCK 050 g 8; DR t
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. j j (2) Technical Specifications
]
The Technical Specifications contained in Appendices.
A and B, as1 revised through: Amendment No. 74, are j
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 and shall be implemented prior to startup from the next refueling outaged scheduled to. start March 1988.
FOR THE NUCLEAR F,EGULATORY COMMISSION.
t' i.
Elinor.-5.Adensam, Director-Project Directorate II-1
(
Division of Reactor Projects I/II.
Attachment:
}
Changes to the Technical j
Specifications 1
Date of Issuance:
November 16, 1987 I
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ATTACHMENT TO LICENSE AMENDMENT N0. 74_
l TO FACILITY OPERATING LICENSE N0. NPF-2 j
DOCKET N0. 50-348 1
l Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages
)
l 3/4 6-10 3/4 6-10
)
B 3/4 6-2 B 3/4 6-2 i
B 3/4 6-2a l
1 l
l 1
l l
I l
1 I
1 l
+
C0'NTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
============================n=================-------==-=======
3.6.1.7 Containment purge supply and ' exhaust valves shall be OPERABLE
- and:
The 48-inch containment purge supply and exhaust isolation valves a.
(CBV-HV-3198A,3198D,3196,3197) shall be de-activated and secured in their closed position.
b.
The 8-inch containment mini-purge supply and exhaust isolation valves (CBV-HV-2866C, 2866D, 2867C, 2867D) may be open for safety-related reasons.
APPLICABILITY:
MODES 1, 2, 3 and a, i
ACTION:
With one 48-inch containment purge supply or one 48-inch containment a.
purge exhaust isolation valve open or.not de-activated, de-activate and secure in the closed position the open valve (s) or isolate the penetration within four hours or be in at least H0T STANDBY within the' i
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With the leakage rate for the containment purge supply and exhaust i
penetrations exceeding the limit of Specification 4.6.1.7.2 or 4.6.1.7.3.a within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> either:
n l
1.
Reduce the leakage to within the limit, or r
2.
Isolate the containment purge supply or both supply and exhaust l
penetrations as required to reduce the leakage rate from the containment atmosphere to the outside atmosphere to within the limit of Specification 4.6.1.7.2 by the use of at least:
a) One OPERABLE de-activated 48-inch inside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch inside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or
- Tnis specification is governing for the containment purge supply and exhaust isolation penetration leakage and 48-inch isolation alve position.
l l
F ARLEY-UNIT 1 3/4 6-10 AMENDMENT NO. ;;, 74
-__--___-_m_.,,
CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
~
b) One OPERABLE de-activated 48-inch' outside containment purge supply or both supply and exhaust isolation. valves secured in the closed position or secured by use of a. blind flange, and,one OPERABLE de-activated 8-inch outside containment' purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or 3.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, c.
With the leakage rate for containment purge supply or exhaust.
.f penet rations. exceeding the limit of Specification 4.6.1.7.3.b, reduce the~ leakage to within the'11mit:
)
(
1.
Prior. to entering A0DE. 4 following the next. COLD SHUTDOWN if the existing leakage. is ' determined during quarterly testing pursuant to Specification 4.6.1.7.2, or 2.
Prior to entering MODE 4 if excess leakage is determined during COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.
SURVEILLANCE REQUIREMENTS
- - - -- - - - --- - -.- - - -.o.- -..-... _____
T 4.6.1.7.1 The 48-inch containment purge supply and exhaust isolation valves y
shall be determined de-activated in the closed position at-least once per 31 days.
5 4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and 48-inch containment purge supply and exhaust isolation valves-with resilient 1-material seals shall be demonstrated'0PERABLE. by verifying that when the ' leakage rates from degradation tests for both penetrations are added to the leakage rates determined pursuant to Specification.4.6.1.2.d for-all other valves and penetrations subject to Type B and C tests, the combined leakage rate is less than or equal to 0.60 La-l FARLEY-UNIT 1 3/4 6-10a AMENDMENT NO. 74 l
l l
i
a i-
4 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM r
SURVEILLANCE REQUIREMENTS (Continued)
.....................===============================u--
-====.
Each containment purge supply and exhaust penetration cont'alning isolation valves with resilient material seals shall be demonstrated OPERABL 4.6.1.7.3 prior to startup after each COLD SHUTDOWN, if not performed in the previous 92 i
days, by verifying that:
a) When the measured leakage rate is added to the leakage rates determined i
pursuant to Specification 4.6.1.2.d for all other valves andpe less than or equal to 0.60 La, and b) The leakage rate for each containment purge supply and exhaust penetration is less than or equal to 0.05 La-In addition, the leakage rate for the containment purge isolation valves.shall 9
be compared to the previously measured leakage rate (for the containment purgeAn eng isolation valves) to detect excess valve degradation.
shall be performed to determine what corrective action, if any, is necessary.
The resilient material valve seals of the 48-inch and the 8-inch 4.6.1.7.4 containment purge supply and exhaust isolation valves shall be replaced at least once per 5 years.
I 1
l l
1 AMENDMENT N0. 33, 74 l l
3/4 6-100 FARLEY-UNIT 1 l
4
^
CONTAINMENT SYSTEMS BASES
-===
l The maximum peak pressure expected to be obtained from a LOCA event is 45 j
The limit of 3 psig for initial positive containment pressure will limit
}
psig.
the total pressure to 48 psig which is less than design pressure and is J
consistent with the accident analyses.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for s LOCA or steam line
]
l break accident.
1 3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY l
This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of l
l Structural integrity is required to ensure that the containment the facility.
will withstand the maximum pressure of 48 psig in the event of a LOCA. The measurement of the containment lift off force, visual examination of tendons, l
anchorages and exposed interior and exterior surf aces of the containment, and the Type A leakage test is sufficient to demonstrate this capability.
The surveillance requirements for demonstrating the containment's l
l structural integrity are in compliance with the recommendations of paragraph l
C.1.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in r
j
}
Prestressed Concrete Containment Structures," January 1976.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are
~
required to be closed in MODES above COLD SHUTDOWN since these valves have not l
been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves closed during plant operations ensures that l
excessive quantities of radioactive materials will not be released via the containment purge system.
The use of the containment purge lines is restricted to the 8-inch vent supply and exhaust isolation valves to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-coolant accident during venting operations.
FARLEY-UNIT 1 B 3/4 6-2 AENDENT NO. 26,70,74 1L -
CONTAINMENT SYSTEMS BASES Ozzssssssssssssssssssssssssssssssssssssssazzassasssssssssssssssssmuszusssssssssas 1
Safety-related reasons for venting containment during operation (MODES 1, j
2, 3 and 4) include controlling containment pressure and reducing airborne radioactivity.
The purpose of the quarterly degradation tests of the isolation valves in the containment purge supply and exhaust lines per Specification 4.6.1.7.2 is to -
{
identify excessive degradation of the resilient seals for these valves.
l In addition, these degradation tests are not subject to the requirements l
applicable to 10CFR50 Appendix J testing but are to be utilized to provide reasonable assurance that at least one set (inside containment or outside containment) of isolation valves provides a sufficient barrier to containment leakage. Tnese degradation tests do not replace Appendix J testing, but are
)
performed in addition to the Type C tests required by Appendix J.
Type C testing that is conducted pursuant'to Specification 4.6.1.7.3 will conform to
]
the requirements of Appendix J., Failure to satisfy the containment purge supply and exhaust isolation valve leakage rate specifications while in MODES 1-4 will be governed exclusively by the ACTION requirements of Specification 3.6.1.7 and l
not by other specifications, t
The 12-hour time limit in ACTION Statement b provides the necessary time to l
confirm tnat containment integrity exists or to take appropriate corrective action.
Isolation of a penet von with leakage in excess of the limit by use of an OPERABLE valve or a blinu flange allows maintenance to be performed on the inoperable valve in that penetration. ACTION Statement b.2 requires a
]
determination be made that the leakage rate from the containment atmosphere to the outside atmosphere is less than or equal to the margin available to 0.60 La; however, it does not require quantification of the leakage, l
I 1
i FARLEY-UNIT 1 B 3/4 6-2a AMENDMENT NO. 74 l
a o nog'o,,
8 UMTED STATES
~
8 NUCLEAR REGULATORY COMMISSION n
E WASHINGTON, D. C. 20555 r
b.,. 4r q
s ALABAMA POWER COMPANY DOCKET NO. 50-364 1
JOSEPHM.FARLEYNUCLEARPLANT,UNITJ l
AMENDMENT TO FACILITY OPERATING LICENSE
]
Amendment No. 66 License No. NPF-8 J
-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee), dated May 4, 1987, complies with the standards'and
'l requirements of the Atomic Energy Act of 1954, as amended 3
(the Act), and-the Commission's rules and regulations set i
l forth in 10 CFR Chapter I-B.
The facility will operate in conformity with the application the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by
.j this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted i
s L
in compliance with the Conrnission's regulations, i
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have i
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 l
amended to read as follows:
i I
. l (2) Technical. Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, 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 and shall be implemented within 30 days of receipt of the amendment.
FOR THE NUCLEAR REGULATORY COMMISSION l
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: November 16, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 66 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 q
f
)
j Replace the following pages of the Appendix "A" Technical Specifications The revised pages are identified j
with the enclosed pages es indicated.
by amendment number and contain vertical lines indicating the area of change.
j i
Insert Pages Remove Pages 3/4 6-10 3/4 6-10 3/4 6-10a 3/4 6-10b B 3/4 6-2 8 3/4 6-2 B 3/4 6-2a j
l 1
l 1
4
l C0'NTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM f
LIMITING CONDITION FOR OPERATION
==
c=========================================================-
.j Containment purge supply and exhaust. valves shall be OPERABLE
- and:
3.6.1.7 The 48-inch containment purge supply and exhaust isolation valves (CBV-HV-3198 A, 3198D, 3196, 3197) shall be de-activated and secured in l
a.
their closed position.
The 8-inch containment mini-purge supply and exhaust isolation valves (CBV-HV-2866C, 28660, 2867C. 28670) may be open for safety-related
{
b.
reasons.
i l
APPLIC ABILITY : MODES 1, 2, 3 and 4,
ACTION:
With one 48-inch containment purge supply or. one 48-inch containment purge exhaust isolation valve open or not de-activated, de-activate and a.
secure in the closed position the open valve (s) or isolate the penetration within four hours or be in at least HOT STANDBY within the j
I next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With the leakage rate for the containment purge supply and exhaust b.
penetrations exceeding the limit of Specification 4.6.1.7.2 or l
4.6.1.7.3.a within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> either:
1 r
1.
Reduce the leakage to witnin the limit, or l
f 3
Isolate the containment purge supply or both supply and exhaust 2.
i penetrations as required to reduce the leakage rate from the containment atmosphere to the outside atmosphere to within the l
limit of Specification 4.6.1.7.2 by the use of at least:
a) One OPERABLE de-activated 48-inch inside containment purge supply or both supply and exhaust isolation valves secured in l
the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch inside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or
- This specification is governing for the containment purge supply and exhaust i
isolation penetration leakage and 48-inch isolation valve position.
FARLEY-UNIT 2 3/4 6-10 AMENDMENT NO.
M,66
_ _ - _ _ _ = _ - _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ -
C0'NTAlNMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION
= - - - - - - - - - - - - - - - -
b) One OPERABLE de-activated 48-inch outside containment 'p'u'rge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, and one OPERABLE de-activated 8-inch outside containment purge supply or both supply and exhaust isolation valves secured in the closed position or secured by use of a blind flange, or 3.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With the leakage rate for containment purge supply or exhaust c.
penet rations exceeding the limit of Specification 4.6.1.7.3.b, reduce the leakage to within the' limit:
1.
Prior to entering MODE 4 f ollowing the next COLD SHUTDOWN if the existing leakage is determined during quarterly testing pursuant to Specification 4.6.1.7,2, or 2.
Prior to entering MODE 4 if excess leakage is determined during h
COLD SHUTDOWN pursuant to Specification 4.6.1.7.3.
SUP.VEILLANCE REQUIREMENTS f
4.6.1.7.1 The 48-inch containment purge supply and exhaust isola ion valves 4
shall be determined de-activated in the closed position at least once per 31 5
days.
4.6.1.7.2 At least once per 92 days, each penetration containing 8-inch and 48-inch containment purge supply and exhaust isolation valves with resilient material seals shall be demonstrated OPERABLE by verifying that when the leakage rates from degradation tests for both penetrations are added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other valves and penetrations subject to Type B and C tests, the combined leakage rate is less than or equal to 0.60 La-1 FARLEY-UNIT 2 3/4 6-10a AMENDMENT NO. 66
1 C0'NTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued) j i
4.6.1.7.3 Each containment purge supply and exhaust penetration containing isolation valves with resilient material seals shall be demonstrated OPERABLE l
prior to startup after each COLD SHUTOOWN, if not performed in the previous 92 days, by verifying that:
a) baen the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other valves and j
(
penetrations subject to Type B and C tests, the combined leakage rate is j
less than or equal to 0.60 La, and b) The leakage rate for each containment purge supply and exhaust penetration is less than or,, equal to 0.05 La-In addition, the leakage rate fo.r the containment purge isolation valves shall be compared to the previously measured leakage Iate (for the containment purge isolation valves) to detect excess valve degradation.
An engineering evaluation -
shall be performed to determine what corrective action, if any, is necessary.
4.6.1.7.4 The resilient material valve seals of the 48-inch and the 8-inch containment purge supply and exhaust isolation valves shall be replaced 'at least j
once per 5 years.
l
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FARLEY-UNIT 2 3/4 6-10b AMENDMENT NO. 6 6
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i
,l
_________O
i CONTAINMENT SYSTEMS il BASES
...........c....==..
The maximum peak pressure. expected to be obtained from a LOCA event is 45 The limit of 3 psig for initial positive containment pressure will limit
{
psig.
the total pressure to 48 psig which is less than design pressure and is consistent with the accident analyses, j
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.
I f
3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY.
This limitation ensures that the structural integrity of the containment l
will be maintained comparable to the original design standards fur the life of 1
the facility. Structural integrity is required to ensure.that the containment will udthstand tne maximum pressure of 48 psig in the event of a LOCA. The visual examination of tendons, anchorages and exposed interior and exterior l
surf aces of the containment, and the Type A leakage test, along with the data
{
obtained from Unit 1 tendon surveillance, is sufficient to demonstrate this J
capability.
d The surveillance requirements for demonstrating tha containment's j
structural integrity are in compliance with the recommendations of paragraph C.1.3 of Regulatory Guide '1.36 " Inservice Surveillance of Ungrouted Tendons in j#
n i
Prestressed Concrete Containment Structures," January 1976.
3 /4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are i
i required to be closed in MODES above COLD SHUTDOWN since these valves have not been demonstrated capable of closing during a LOCA or steam line break 4
^
accident. Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.
The use of the containment purge lines is restricted to the B-inch vent supply and exhaust isolation valves to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a' loss-of-coolant accident during venting operations.
1 FARLEY-UNIT 2 B 3/4 6-2 AMENDMENT N0. 34, 66
1 CONTAINMENT SYSTEMS BASES 1
Safety-related reasons for venting containment during operation (MODES 1, f
2, 3 and 4) include controlling containment pressure and reducing airborne radioacti vity.
The purpose of the quarterly degradation tests of the isolation valves in the containment purge supply and exhaust lines per Specification 4.6.1.7.2 is to identify excessive degradation of the resilient seals for these valves.
In addition, these degradation tests are not subject to the requirements I
applicable to 10CFR50 Appendix J testing but are to be utilized to provide j
reasonable asprance that at least one set (inside containment or outside l
containment) of isolation valves provides a sufficient barrier to containment-leakage. These degradation tests do not replace Appendix J testing, but are-performed in addition to the Type C, tests required by Appendix J.
Type C testing that is conducted pursuant'to Specification 4.6.1.7.3 will conform to-the requirements of Appendix J.. Failure to satisfy the containment purge supply and exhaust isolation valve leakage rate specifications while in MODES 1-4 will be governed exclusively by the ACTION requirements of Specification 3.6.1.7 and not by other specifications.
The 12-hour time limit in ACTION Statement b provides the necessary time to confirm that containment integrity exists or to take appropriate corrective action.
Isolation of-a penetration with leakage in excess of the limit.by use of an OPERABLE valve or a blind flange allows' maintenance to be performed on the inoperable valve in that penetration. ACTION Statement b.2 requires a
~
I determination be made that the leakage rate from the containment atmosphere to the outside atmosphere is less than or equt.1 to the margin available to 0.60 La; l
however, it does not require quantification of the leakage.
~
k i
FARLEY-UNIT 2 B 3/4 6-2a AMENDMENT NO. 66,
-_-__--.______----_-__-___m_
m
_