ML20085N695
| ML20085N695 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/10/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085N699 | List: |
| References | |
| NUDOCS 9111180047 | |
| Download: ML20085N695 (9) | |
Text
.
4 pc as cy'o, UNITED STATES a
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,n NUCLEAR REGULATORY COMMISSION 3m O'
t WASHINGTON, D. C. 20555 o.,
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PUBLIC SERVICE C0t'PANY OF NEW HAMPSHIPE, ET,A,L.*
DOCKET NO. 50-443 SEABROOK ST ATJpR,, U,NJ T, Np,.,1
.AM.EFp!1,Ep,T,,Tp, ff _CJ LJ,T,Y, p P E R AT I NG L I C E N S E Amendment No. 7 License fo. NPF-86 1.
The Nuclear Regulatory Concission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Company of New Hampshire (the licensee), acting for itself and as agent and representative of the 11 other utilities listed below and hereafter referred to as licensees, dated January 24, 1991, 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 replations 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 set forth in 10 CFR Chapter I; 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 IC CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- Public S'e'rvice Company of New Hampshire is authorized to act as agent for the:
Canal Electric Company, The Connecticut Light and Power Company, EUA Power
-Corporation, Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The United Illuminating Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9111100047 913o3o PDR ADOCK 05000443 P
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2.
Accordirgly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(?) of Facility Operating License No. NPF-86 is hereby amended to read as follows:
(2) Technical Sp,e,cifications The Technical Specifications contained in Appendix A, as revised through Amendrrent No.
7, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility !.itense ff9, NPF-86. PSNH siall operate the facility in accordance with'the Technical Specifications and the Environmental Protection Plan.
3.
This license emendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR TPE NUCLEAR REGULATORY C0f4MISS10tl (jf W
Walter R. Butler, Director Project Directorate 1-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 10, 1991 I
p_..
ATTACHMENT TO LICEf4SE AMENDMEtiT fl0. 7 FACILITY OPERATitlG LICEllSE 110. IlPF-86 00CKET tl0. 50,-443 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and
- ontain vertical lines indicating the area of change.
Overleaf pages have been provided for your convenience.
Remove Insert 1-2 1-2 1-3 1-3 1-4 1-4 1-5 1-5 2
1-6 1-6 1-7 1-7 3/4 3-59 3/4 3-59 3/4 3-66 3/4 3-66 i
r
1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.
ACTUATION LOGIC TEST 1.2 An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock icgic state and verification of the required logic output.
The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.
ANALOG CHANNEL OPERATIONAL TEST
- 1. 3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions.
The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip 5etpoints such that the Setpoints are within the required range and accuracy.
AXIAL FLUX OIFFERENCE
- 1. 4 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.
CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the odjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any. series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK l
1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same para +ter.
1 SEABROOK - UNIT 1 1-1
DEFINITf0NS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions.
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
' : sealing mechanism associated with each penetration (e.g., welds, bellows, er 0-rings) is OPERABLE.
CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and/or injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.
The Digital Channel Operational Test definition is only applicable to the Radiation Monitoring Equipment.
DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in NRC Regulatory Guide 1.109, Revision 1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I."
E - AVERAGE DISINTEGRATION ENERGY 1.12 E shall be the average (weighted in proportion to the concentration of l
each radionuclide in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample with half-lives greater than 10 minutes.
SEABROOK - UNIT 1 1-2 Amndment No. 7
DEFINITIONS ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time l
interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times-shall include diesel generator starting and sequence loading delays where applicable.
FREQUENCY NOTATION 4
1.14 The FREQUENCY NOTATION specified for the performance of Surveillance l
Requirements shall correspond to the intervals defined in Table 1.1.
l GASE0US RADWASTE TREATMENT SYSTEM 1.15 A GASE0US RADWAS'IE TREATMENT SYSTEM shall be any system designed and l
installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing-the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE l
1.16 IDENTIFIED LEAKAGE shall be:
a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tak, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay.
The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER (5) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-l i
tionally associated with the plant.
This category does not include employees of the licensee, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.
SEABROOK - UNIT 1 1-3 Amendment No. 7
DEFINITIONS i
0FFSITE DOSE CALCULATION MANUAL 1.19 The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain in Part A the l
radiological effluent sampling and analysis program and radiological environ-nental monitoring program.
Part B of the ODCM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.
OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or I
have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 1.21 An 0PERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive I
combination of core reactivity condition, power level, and average reactor coolant-temperature specified in Table 1.2.
PHYSICS TESTS 1.22 PfiYSICS TESTS shall be those tests performed to measure the fundamental l
nuclear characteristics of the reactor core and related instrumentation:
(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube l
leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
PROCESS CONTROL PROGRAM 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, l
sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and i
Federal and State Regulations, burial giound requirements, and other require-ments governing the disposal of radioactive waste.
PURGE - PURGING 1.25 PURGE or PURGING shall be any controlled process of discharging air or gas l
from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
l l
SEABROOK - UNIT 1 1-4 Amendment No, 7 L
L. - - - -
DEFINITIONS QUADRt,NT POWER TILT RATIO 1.26 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore l
detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
With one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATED THERMAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to l
the reactor coolant of 3411 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter axceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in l
Section 50.73 of 10 CFR Part 50.
CONTAINMENT ENCLOSURE BUILDING INTEGRITY 1.30 CONTAINMENT ENCLOSURE BUILDING INTEGRITY shall exist when:
a.
Each door in each access opening.is closed except when the access opening is being used for normal transit entry and exit, b.
The Containment Enclosure Filtration System is OPERABLE, and c.
The-sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.
SHUTDOWN MARGIN 1.31 SHUTOOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.32 The SITE B0UNDARY shall be that line beyond which the land is neither l
owned, nor leased, nor otherwise controlled by the licensee.
l SEABROOK - UNIT 1 1-5 Amendment No. 7 l
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DEFINITIONS SLAVE RELAY TEST 1.33 A SLAVE RELAY TEST shall be the energization of each slave relay and I
verification of OPERABILITY of each relay.
The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
SOLIDIFICATION 1.34 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.35 A SOURCE CHECK shall be the qualitative assessement of channel response I
when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.36 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
THERMAL POWER 1.37 THERMAL POWER shall be the total reactor core heat transfer rate to the j
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and ver1.ying OPERABILITY of alarm, interlock and/or trip functions.
The TRIP ACTUAlING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE l
or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.40 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not coni. rolled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
SEABROOK - UNIT 1 1-6 A~endment No. 7
DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM 1.41 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and l
installed to reduce gaseous radiciodine or radioactive material in particulatt form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particu-lates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.42 VENTING shall be-the controlled process of discharging air or gas from a l
confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
I SEABROOK - UNIT 1 1-7 Amendment No. 7
TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
H At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
N.A.
Not applicable.
P Completed prior to each release.
TABLE.1.2 OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT HODE CONDITION, k THERMAL POWER
- TEMPERATURE eff 1.
POWER OPERATION N 0.99
> 5%
> 350 F 2.
STARTUP i 0.99
~< 5%
5 350*F 3.
HOT STANDBY i 0.99 0
5 350*F 350 F > T,yg > 200*F 4.-
HOT SHUTDOWN
< 0.99 0
5.
COLD SHilTDOWN
< 0.99 0
~< 200 F 6.
REFUELING **
< 0.95 0
140 F
- Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
i SEABROOK - UNIT-1 1-8
TABLE 4.3-5 (Continued)
~
TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the normal or surveillance test Alarm / Trip Setpoint.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial ~ calibration shall be used.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(4) CHANNEL CHECK shall consist of verifying indication of tank level during
_ periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b SEABROOK - UNIT 1 3/4 3-59 Amendnent No. 7
INSTRUMENTAT20N MONITORING INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
[
LIMITING CONDITION FOR OPERATION
- 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels
- shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.
The Alarm / Trip Setpoints of these channels meeting-Specification 3.11.2.1
- shall be determined and adjusted in accordance with the fiethodology and parameters in the ODCH.
APPLICABILITY:
As shown in Table 3.3-13.
ACTION:
a.
With-a radioactive gaseous effluent mnnitoring instrumentation channel Alarm / Trip Setpoint -less conservative-than required by the above specification, immediately surpend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.
b.
With the number of OPERABLE radicactive gaseous effluent monitoring instrumentation channels'less than the Minimum Channels OPERABLE, take the_ ACTION shown in Table 3.3-13.
Restore thc inoperable instrumentation to OPERABLE status within 30 days on. if-unsuccessful, explain cin-the next Semiannual Radioactive Effluent Release Report pursuant to' Specification 6.8.1.4-why this inoperability was not corrected in a timely manner.
c.
-The provisions of Specification 3.0.3 are not applicable.
t
- SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall-be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.
I l
i.
I l
l SEABROOK - UNIT 1 3/4 3-60 y..
TABLE 4.3-6 (Continued) u, O
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUTREMENTS EE 4
SE CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE E
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
_w sa 3.
GASEOUS WASTE PROCESSING SYSTEM (Providing Alarm and Automatic Termination of Release)
- a. Noble Gas Activity Monitor D
N.A.
R(5)
Q(1)
(Process) 4.
TURBINE GLAND SEAL CONDENSER EXHAUST
- a. Iodine Sampler W
N.A.
N.A.
N. A f
- b. Particulate Sampler W
N.A.
N.A.
N.A.
- c. Sampler Flow Rate Indicator D
N.A.
N.A.
N.A.
0 T
TABLE 4.3-6 (Continued)
TABLE NOTATIONS
'At all times.
During RADI0 ACTIVE WASTE GAS SYSTEM operation.
When the gland seal exhauster is in operation.
- The CHANNEL OPERATIONAL TEST for the flow rate monitor shall consist of a verification that the Radiation Data Management System (RDMS) indicated flow is consistent with the operational status of the plant.
Noble Gas Monitor for this release point is based on the main condenser air evacuation monitor.
(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the normal or surveillance test Alarm / Trip Setpoint.
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels abovc the normal or surveillance test Alarm Setpoint.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall per-mit calibrating the system over its intended range of energy and measure-ment range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
a.
One volume percent oxygen, balance nitrogen, and b.
Four volume percent oxygen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall be performed using sources of various activities covering the measurement range of the monitor to verify that the response is linear.
Sources shall be used to verify the monitor response only for the intended energy range.
i SEABROOK - UNIT 1 3/4 3-66 Amendment No. 7 i
4
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