ML20154E273
| ML20154E273 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/12/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154E277 | List: |
| References | |
| TAC-68686, TAC-68687, NUDOCS 8809160276 | |
| Download: ML20154E273 (22) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. OPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. OPR-57 filed by Georgia Power Company, acting for itself Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated June 20, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (i) that the activities authorited 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 set forth in 10 CFR Chapter I; D.
The issuance of this 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.
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 12, 1988
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ATTACHMENT TO LICENSE AMENDMENT N0.
156 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following sages of the Appendix A Technical Specifications with the enclosed pages.
T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Page Insert Page 3.2-66 3.2-66 3.12-2 3.12-2 3.12-3 3.12-3 3.12-4 3.12-4 3.12-5 3.12-5 3.12-6 3.12-6 l
BASES FOR LIMITING CONDITION 3 FOR OPERATION
- ~ ~ ~ ~
occurs with each monitor indicating HI H! HI, one monitor H! HI H! and the other downscale, or with both monitors downscale. The HI H! H! Setpoint cer-responds to the instantaneous release limit.
2.
Refuelina Floor Exhaust Vent Radiation Monitors Four radiation monitors are provided which initiate isolation of the second-ary containment and operation of the standby gas treatment system. The in-strument channels monitor the radiation from the refueling area ventilation exhaust ducts.
Two instrument channels with two radiation monitors in each channel are ar-ranged in a two upscale (either channel) trip logic. Trip settings for the monitors in the refueling floor exhaust ventilation ducts are based upon ini t1ating normal ventilation isolation and standby gas treatment system opere-tion so that none of the activity released during the refueling accident le; the reactor building via the nornel tent 11ation path but rather all the ac-tivity is processed by the standby gas treatment system.
3.
Reactor Buileine Exhaust Ven: Radiation Moniters Four radiation monitors are provided which initiate secondary containment iso-lation, primary containment purge and vent valves isolation and standby gas treatment system actuation. The instrument channels monitor the radiation from the reactor building lower level ventilation exhaust duct.
Two instrument channels with two radiation detectors in each channel are ar-ranged in a two upscale (either channel) trip logic. The trip settings are based on limiting the release of radioactivity via the norwul ventilation path and rerouting this activity to be processed through the standby gas treatment system.
4.
Control Room Intake Radiation Monitors Two radiation monitors are provided to initiate pressurization of the main l
control room and recirculation of control room air through filters. The instrument channels monitor radiation from the control room ventilation intake duct.
Two instrument channels are arranged in one upscale, two downscale trip log-ic. The trip settings are based on limiting the radioactivity from enterint, the control room from outside.
5.
Main Steam line Radiation koititors Although their primary function is to close the M51Vs. the four Main $ team Line radiation monitors also initiate isolation of the mechanical vacuum Duc4 and the gland seal exhauster condenser. The instrument channels monitor the radiation in the main steam line tunnel. The purpose of automatica1'y 150-lating the mechanical vacuum puso line is to provide timely protection agair*/
the release of radioactive materials f rom the main condenser. Upon receipt of main steam line high radiation signals, the primary containment and reac-
- r vessel isolation control system initiates closure of the mechanical vac-uum pump line valve. This isolation precludes or limits the release of fis-tion product radioactivity which, upon fuel failure would be transported from HATCH - UNIT 1 3.2-66 Amendment No. 156 i
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LIMITING CONDITION 5 FOR OPERATION SURVEILLANCE REQUIREMENT 5 3.12.A.2.
Performance Reautrements 4.12.A.2.
Filter Testina a.
The results of the in-place a.
The tests and analysis 00P and halogenated hydro-shall be performed at carbon tests at design flows least once per operating on HEPA filters and charcoal cycle, not to exceed 18 absorber banks shall show months, or after every 199-percent 00P removal and 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system opera-199-percent halogenated tion or following painting, hydrocarbon removal, respec-fire or chemical release in tively when tested in accordance any ventilation zone conseuni with AN$1 N510-1975.
cating with the system.
b.
The results of laboratory b.
00P testing shall be per-carbon sample analysis formed after each complete shall show 190-percent radio-l or partial replacement of active methyl iodide the HEPA filter bank or removal when tested in after any structural accordance with ROT-M16-1T maintenance on the system (25'C, 95-percent R.H.).
l housing.
l c.
Fans shall be shown to i
c.
Halogenated hydrocarbon operate within 110-percent l
testing shall be performed design flow when tested after each complete or in accordance with AN$!
partial replacement of the N510-197 5.
charcoal adsorber bank of after any structural maintenance on the system housing.
B.
tholation Valve Operability and 8.
Isolation Valve festina C os' no Time (Deleted)
(Deleted) l l
l HATCH - UNIT 1 3.12-2 Amendment No. 156 l
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,A LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.12.C.
Radiation Monitors 4.12.C.
Radiation Monitors The control room air intake The control room air intake radiation monitors or suitable radiation monitors shall be respective temporary units shall tested in accordance with be operable whenever the venti-Table 4.2-8.
lation system is required to be operable by Specification 3.12. A.1.
except that one radiation monitor may be out of service 30 days.
D.
Shutdown Reauirements In the event that Specifications 3.12.A. through 3.12.C. cannot be met, the reactor shall be placed in the Cold Shutdown Condition with-in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or, if refueling opera-tions are in progress, such opera-tions will be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
E.
Chlorine konitors E.
Chlorine Monitors (Deleted)
(Deleted)
HATCH - UN!T 1 3.12-3 Amendment No. 156
1 3 12. MAIN CONTROL ROOM ENVIRONMENTAL SYSTEM The control room air treatment system is designed to filter the control
, room atmosphere for intake air and/or for recirculation during pressurization conditions.
A.
Ventilation System Operability Reauirements The control room air treatment system operates on emergency power and is designed to filter the control room atmosphere for intake air and or recirculation air during control room pressurization conditions.
l The control room air treatment tystem is designed to automatically start upon receipt of an initiation signal and to align the system dampers to provide for pressurization of the control room.
Pressurization will be initiated upon receipt of any one of the follow-ing signals: High radiation at control room intake, LOCA signal from Unit 1 or 2 main steam line high radiation from Unit 1 or 2, main steam line high flow from Unit 1 or 2, or refueling floor high radiation f rom Unit 1 or 2.
In this mode the nornel control room exhaust fan 13 stopped and outside air is taken in througn one of the charcoal filters to pressurize the control room with respect to the surrounding turbine building.
I High ef ficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential intake of radiciodine to the control room. Oypass leakage for the charcoal adsorbers and particulate removal ef ficiency for HEPA filters are determined by halogenated hydrocarbon and 00P, respectively. The laboratory carbon sample test results indicate a radioactive methyl iodide removal efficiency for expected accident conditions. Opera-tion of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsor-bers. if the performances are as specified, the calculated doses would be less than the allowable levels stated in Criterion 1g of the General Design Criteria for Nuclear Power Plants Appendix A to 10 CFR Part 50.
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i HATCH - UNIT 1 3,12-4 Amendment No. 156 i
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8.
Isolation Valve Ocorability and Closino Time (Oeieted>
C.
Radiation Monitors At least one channel (detector) in the control room air intake radia-tion monitoring system must be operable at all times for indication-alarm of radioactivity being deawn into the main control room. Main control room intake air filtration is required when a trip signal f rom the detectors is given via failure or pressurization signals from both channels or a failure signal in one channel and a pressurization signal in the other channel.
O.
Shutdown Recuirements Shutdown requirements are based on the need to ensure habitability for operations personnel during normal plant operation and subse-quent to a postulated design basis accident.
F.
Chlorine Monitors (Deleted) 4.12.
MAIN CONTROL ROON ENVIRONMENTAL SYSTEM A.
Ventilation System Tests Pressure drop across the combined HEPA filters and charcoal adsorbers of less than P. in, of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter. A test f requency of once per operating cycle established system performance capability, i
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HATCH - UNIT 1 3.12-5 A=cndment No. 156 l
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The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated.
Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52.
The charcoal adsorber efficiency test procedures shall allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thoroughly and obtain-ing at least two samples. Each sample should be at least 2 in, in diameter and a length equal to the thickness of the bed. If the iodine removat ef ficiency test results are unacceptable, all adsorbent in the system should be replaced. Any HEPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system every month will demonstrate operability of the filters and adsorber system. Operation for 15 minutes demon-strates operability and removes the moisture build-up during testing.
If painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated f rom the fumes, chemi-cals or foreign materials, the same tests and sample analysis should be perforsed as required for operational use.
Demonstration of the automatic initiation capability is necessary to assure system performence capability.
B.
Isolation Valve Testina i
(Deleted)
C.
Radiation Bases for the control room air intake radiation monitors are specifi-cally discussed in Bases for Limiting Conditions for Operation, Speci-fication 3.2.H.4., and are generally discussed in Bases for Surveillance Requirements, Specification 4.2.
l 0.
References 1.
(Deleted) 2.
(Deleted) 3.
ANSI Standard N101.1,1972, 'Ef ficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particulates'.
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i HATCH - UNIT 1 3.12-6 Amendeent No. 156 i
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2 ANENOMENT TO FACILITY OPERATlHG LICENSE Amendment No. 96 License No. NPF-5 r
1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the Edwin 1. Hatch Nuclear Plant, A.
Unit 2 the facility) Facility Operating License No. NPF-5 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Munici >al Electric Authority of Georgia, and City of Dalton, Georgia, (tie licensee) dated June 20, 1988, complies with the standards and requirernents of the Atomic Energy Act of 1954, as arnended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this smendment 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 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 Cosmission's regulations and all applicable requirements have been satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. !!PF-5 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, 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 implenwnted within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COPEISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Attachtent:
Changes to the Technical Specifications Date of Issuance:
September 12, 1988
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following lages of the Appendix A Technical Specifications with the enclosed pages. T1e revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Page Insert Page 3/4 3-58a 3/4 3-58a 3/4 3-58b 3/4 3-5Bb 3/4 3-58c 3/4 3-58c 3/4 3-58d 3/4 3-5Bd 3/4 7-6 3/4 7-16 3/4 7-7 3/4 7-7 3/4 7-8 3/4 7-8 8 3/4 3-4 B 3/4 3-4 4
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TABLE 3.3.6.7-1 (SHEET 2 0F 2)
MCRECS ACTUATION INSTRUNENTATION ACTION ACTION 52 Take the ACTION required by Specification 3.3.3.
ACTION 53 Take the ACTION required by Specification 3.3.2.
ACTION 54 With one of the required radiation monitors inoperable, restore the a.
monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the MCRECS in the pressurization mode of operation.
b.
With no radiation monitors OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the MCRECS in the pressurization mode of operation.
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The provisions of Specification 3.0.4 are not applicable.
c.
NOTES When handling irradiated fuel in secondary containment, A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a.
required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter, b.
With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPEAA8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken, Actuates the MCRECS in the control room pressurization mode.
c.
d.
(Deleted)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test e.
with the reactor power at greater than 20-percent rated power, the normal l
i full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20 percent rated power.
HATCH = (JNIT 2 3/4 3-58b Amendment No. 96 i
TABLE 3.3.'6.7-2 D
8eCstfC5 ACTUAfloat INSTRupe[4 TAT 80el SETPoleTS n
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Tater FussCTIces Trip SE1 POINT ALLOWASLE VALK E1 Reacter Vesset lister Level -
2 -113 laches Q
Lew Low Lew (Level 1) 2 - 113 Inches 2.
Drywell Pressure - Niges N
5 1.92 psig i 1.92 psig 3.
seeln Steam L8mo Aedletten - Nigh 1 3 x rull-power techground*
1 3 x rull powr background
- 6 see 8m Steam Line flew - Nigan 1 1341 rated reew s 134% rated riew S.
meruellag fleer Area Aedlellen - Mig 8e 5 20 er/ hour 120 er/ hour 6.
Congres Asem Air Inlet Radletlen - Nigth i 1 er/ hour i 1 er/ hour l
g 1
- a n
- tdithin 24s hours prior to the planned start er the hydrogen injection test with the reacter power at greater then 20-percent p
- c. rated power, the normel rut a power radiation background l
{ calculated value er the radiation levet expected during the test.sevel and associated trip setpoints may be changed based on a s
- wtpointe may be adjusted during the test based en either calculations er measurements er actualThe bochground radiation level and asseclated trip 1
resulting Free hydrogen injectlen.
radiation levels 1
she88 be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> er re-establishing normalThe hockground radiation level sheII be determined and associated trip setpoints
=
radiatten levels att6r completion er hydrogen Injection and prior o
l to..t.= s o.in, r cs.r -r i.vei s h. sew 20-perc.nt rat.d - r.
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PLANT SYSTEMS 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS)
LIMITING CONDITION FOR OPERATION 3.7.2 Two independent MCRECS shall be OPERABLE.
APPLICABILITY: CONDITIONS 1, 2, 3, 5, and ".
ACTION:
With one MCRECS inoperable, restore the inoperable system to OPERABLE l a.
status within 7 days or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD 5HUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With bott, MCRECS inoperrble, be in at im: Fl. SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within to ne4*. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.2 Each HCRECS shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifytiig that the control room a.
air temperature is s 105'F.
6.
At least once per 31 days, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
c.
At least once per 18 menths or (1) after any scructural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:
1.
Performing a visual inspection of the system and all associated components before each leak *.est in accordanca with Section 5 of ANSI N510-1975.
l
- When handling irradiated fuel in secon.dary containment.
HATCH - UNIT 2 3/4 7-6 Mencicent No. 96
.m___m------
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52. Revision 1, July 1976, ano tl.a system flow rate is 2500 cfm 10 percent.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1. July 1976, meets the laboratory testing criteria of Regulatory Position C.6.4 of Regula-tory Guide 1.52, Revision 1 July 1976.
4 Verifying a system flow rate of 2500 cfm : 10 percent during system operation when tested in accordance with ANSI N510-1975.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of hegulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide i
1.52, Revision 1, July 1976.
e.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined i
HEPA 'ilters and charcoal adsorber banks is < 6 in.
W. G. while operating the system at a flow rate of 2500 cfm : 10 percent.
l 2.
(Deleted)
I i
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i HATCH - UNIT 2 3/4 7-7 Amendment No. 96 l
1
PLANT SYSTEMS SURVEllt.ANCE REQUIREMENTS (Continued) 3.
Verifying that on each of the below pressurization mode actuation test signals, the system automatically switches i
to the pressurization mode of operation and maintains the main control room at a positive pressure of 4 0.1-in.
j W.G. relative to the adjacent turbine building during system operation at a flow rate s 400 cfm.
a) Reactor vessel water level - low low low b) Drywell pressure - high c) Refueling floor area radiation - high d) Main steam line radiation - high e) Main steam line flow - high i
3 f) Control room intake monitors radiation - high a
f.
After each complets or partial replacement of a HEPA filter I
bank by verifying that the HEPA filter banks remove 199 percent i
of the DOP when they are tested in place in accordance with ANSI l
N510-1975 while operating the system at a flow rate of 2500 j
cfm 1 10 percent.
l I
l l
g.
After each complete or partial replacement of a harcoal adsorber bank by verifying that the charcoal adsorbers remove 1
2 99 percent of a halogenated hydrocarbon refrigerant test gas l
when they are tested in place in accordance with ANSI N510-1975 j
while operating the system at a flow rate of 2500 cfm 2 10 percent.
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i HATCH - UNIT 2 3/4 7-8 Amendment No. 96 1
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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant param-eters to monitor and assess important variable following an accident.
1 3/4.3.6.5 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during startup. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is t
available without the SRMs and they can be retracted, t
3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM The OPERAS'tLITY of the traversing incere probe system with the specified minteum complement of equipment ensures that the measurements obtained from use of this equipment accurately, represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector to be used and normalizing their respective outputs.
i 3/4.3.6.7 MCRECS ACTUATION INSTRUMENTATION L
The OPERABILITY of the MCRECS ensures the necessary protective actions will be automatically initiated to provide protection for control s
room personnel.
3/4.3.6.8 (Deleted) l
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l HATCH - UNIT 2 B 3/4 3-4 Amendmenc No. 96 i
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