ML20212F130
| ML20212F130 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/22/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212F126 | List: |
| References | |
| NUDOCS 9711040191 | |
| Download: ML20212F130 (9) | |
Text
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p UNITED STATES sL
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3044H001
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NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50r?di MILLSTONE NUCLEAR POWER STATION. UNIT 1 AMENDL4ENT_TO FACILITY OPERATING LIC(({1E Amendment No.102 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company (the licensee) dated February 7,1997, as supplemented April 3 and September 19, 1997, 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 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendet it can be conducted without endangering the health and safety of the r.ublic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
'E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I i
9711040191 971022 PDR ADOCK 05000245 p
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- 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. DPR-21 is hereby amended-to-read as follows:
.(2)
Technical-Snacifications-The Technical Specificatisns contained'in' Appendix A, as revised.
-,through Amendment No.107,, 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 the date of issuance, to be
-implemented within' 90_ days of issuance. -
FOR THE NUCLEAR REGULATORY COMMISSION
~
PhillipF.h,cKee Deputy Director for Licensing Special-Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of_: Issuance:
Octcher 22,-1997-L'
.... =.
Y ATTACHMENT TO LICENSE AMENDMENT NO. 102 j
FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replat+ the followin the attached pages. g pages of the Appendix A, Technical Specifications, with The revised pages are identified by amendment number and l
contain vertical lines indicating the areas of change.
Remove Insert 1-1 1-1 1-la 1-8 1-8 3/4 1-1 3/4 1-1 3/4 1-2 3/4 1-2 8 3/4 1-9 B 3/4 1-9 t.
.1.0 DEFINITIONS
- The succeeding frequently used terms are explicitly defined so that.
a uniform interpretation of the Specifications may be achieved.
A.
Deleted
- B.
Core Alterations CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other com>onents affecting reactivity within the reactor vessel with tie vessel head removed-and fuel in the vessel. Movement of source range monitors, local power range monitors, intemediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement) is not considered a CORE ALTERATION.
Suspersion of CORE ALTERATIONS shall not preclude ccmpletion of.
movement of a component to a safe position.
C.
Hot Standby
% T STAND 8Y means operation with the reactor critical, system
-pressure less than 600 psig, and the main steam isolation valvas closed.
D.
Immediate Il04EDIATE means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the l
importance of the required action.
1 E.
Instrument or thannel calibration An INSTRUMENT or CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary ranga and accuracy to known values of the parameter that
- the channel monitors. The INSTRUNENT or CHANNEL CALIBRATION shall encompass those components, such as sensors, alarms, displays, and trip functions, required.to perfom the specified safety function (s). The INSTRUMENT or CHANNEL CALIBRATICN shall include the INSTRUMENT or CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTO) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjust 01e devices in the channel. The INSTRUMENT or CHANNEL CALIBRATION may be performed by means of any' series of sequential, overlapping, or tota 1' channel steps so that the entire channel is calibrated.
F.
Instrument or channel Functional Test An INSTRUMENT or CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual-signal into the channel as close to the sensor as practicable to verify OPERABILITY, including all components in the chtnnel, such as alarms, interlocks, displays, and trip Millstone Unit-1 1-1 Amendment No. 7), pf,102 esa
=
1.0 DEFINITIONS fcontinued)
F.
J.(r;trument or Channel Functional Test (cont'd) functions, required to perform the specified safety function (s).
The INSTRUMENT or CHANNEL FUNCTIONAL TCST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
G.
Instrument Check 1
-An INSTRUMENT CHECK is qualitative determination of operability by observation of behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measurir.g the sar,e variable.
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Nillstone Unit 1 1-la Amendment No. 102 I
osee
- ,[
- 00. Sucolamental Reload Licensina Submittal The SUPPLEMENTAL-RELOAD ~ LICENSING SUBNITTAL_(SRLS), its supplements and revisions, are unit and cycle specific document (s) containing the power distribution limits (MCPR, LhdR. and APLHGR) for the current o nrating cycle.
The limits in the SRLS, including sup le-ments and - revisions, are only applicable during the reload /c cle number (s) given in the title.
These cycle specific limits shal be deters'ned for each reload cycle in accordance with Specification 6.9.1.9.
PP.- Averaae Planar Linear Heat Generation Rate (APLHGR)
The AVERAGE' PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
- hall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified bundle at the specified height, divided by the number of fuel rods in the fuel bundle at that height.
QQ.
Linear Heat Generation Rate (LHGR) i The LINEAR HEAT GENERATION RATE (LHGR) shall be applicable to a specific rod at a specific height and is equal-to the heat genera-tion rate per unit-length for the specific rod at that specific height.
RR.
Limitina Control Rod Pattern A LIMITING CONTROL R0D PATTERN is a control rod configuration which results in the core being on a thermal hydraulic limit, i.e.,
operating on a limiting value for APLHGR, LHGR, or MCPR.
SS. Reactor Protection System (RPS) Lo: sic Resnonse Time The RPS LOGIC RESPONSE TIME shall be that time interval from the opening of the senter contact up to and including the de-energization of the scram pilot valve soler91ds.
]1stoneUnit1 N
1-8 Amendment No. U M. 102
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LIMITING COM ITION FOR OPERATION 3.1 REACTOR PROTECTION SYSTEM Annlicability Applies to the instrumentation and associated devices which initiate a reactor scram and provide automatic isolation of the Reactor Protection System buses from their power supplies.
Obiective:
To assure the operability of the Reactor Protection System.
Snecification:
A.
The setpoints, minimum number of trip systems, and minimum number of '
instrument channels that must be operable'for each position of the reactor mode switch shall be as given in Table 3.1.1.
8.
NOT USED.
l l
C.
Reactor Protection System Pcwer Monitorina Two RPS electric power monitoring channels for each inservice RPS MG set, or l
alternate power supply, shall be operable at all times except as follows:
1.
With one RPS electric power monitoring channel for an inservice RPS MG set or alternate power supply inoperable, restore the inonerable
,chaniel to OPERABLE status within 72 houts or remove ti)e associated 9.PS 14G set or alternate power supply from service.
2.
With both RPS electric power monitoring channels for an inservice RPS MG set or alternate power supply inoperable restore at least one to OPERABLE status within 30 minutes or remo,ve the associated-RPS MG set or alternate power supply from service.
SURVEILLANCE REQUIREMENT
.4.1 REACTOR PROTECTION SYSTEM Annlicability:
Applies to the survelilance of the instrumentation and associated devices which initiate reactor scram and provide automatic isolation of reactor protection system buses from their power supplies.
Millstone Unit 1 3/4 1-1 Amendment No. 102 ono
SURVEILLANCEREQUIREMENTS(Continued) 4.1-REACTOR PROTECTION SYSTEM
{
Ob.iective:
To specify the type and frequency of surveillance to be applied to the i
i reactor protection instrumentation.
Snecification:
A.
Instrumentation systems shall be functionally tested and calibrated as indicated in Tables 4.1.1 and 4.1.2, respectively. Verify the RPS LOGIC RESPONSE TIME for each trip function listed below is within limits at least once every OPERATING CYCLE.
l.-
APRM: Flow Blased High Flux 2.
High Reactor Pressure 3.
High Drywell Pressure.
4.
-Reactor Low Water Level 5.
Main Steam Line Isolation Valve Closure 6.
Turbine Control Valve Fast Closure 7.
Turbine Stop Valve B.
Daily during reactor power operation, the maximum fraction of limiting '
power density shall be checked-'and the APRM scram and rod block settings given by the equations in Specifications 2.1.2A and 2.1.28 shall be determined to be valid.
C.
The RPS electrical protection assemblies shall be determined operable as follows:
1.
At least once per 6 s,onths by performance of a CHANNEL FUNCTIONAL TEST, and 2.-
At least once per 10 months by demonstrating the OPERABILITY of over-voltage, under-voltage and under-frequency protective.
instrumentation by performance of a CHANNEL' CALIBRATION including simulated automatic actuation of the protective relays, tripping logic and output circuit breakers, and verifying the following setpoints:
a.
- Over-voltage s (132)VAC, b.
Under-voltage 2 (106)VAC, c.
Under-frequenc
- d. -
Time-delay g (y 2)(57)Hz, and 4.0 seconds.
D.
When the reactor mode switch is in REFUEL or SHUTDOWN and fuel is in the reactor vessel, no trip functions are required to be operable provided that all control rods are fully inserted, and either electrically or hydraulically disanned. Thereafter, daily surveillance shall be performed to verify that all control rods remain valved out or electrically disarmed.
Millstone Unit 1 3/4 1-2 Amendment No. 102 em
o e.
4.1 AEACTOR PROTECTION SYSTEN l
BASES Group (C) devices are active only during a given portion of the operational cycle.
For example, the IRM is active during startup and inactive during full-power operation.
Thus, the only test that is meaningful is the one perfomed just prior to shutdown or startup; i.e., tha tests that are performed just prior to' use of the instrument.
the condenser Low Vacuum trip is treated differently.While included in Group (C),
This is because the condenser low vacuum trip sensor can only be tested during shutdown.
The primary function of this trip is to protect the turbine and condenser, although it is cannected into the reactor protection system; thus testing the sensor at each refueling _ outage is adequate.
Calibration frequency of the instrument channels is divided into two groups.
These are as follows:
Passive type indicating devices that can be compared with like units a.
on a. continuous basis, b.
Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity.
i Experience with passive type instruments in generating stations and i
substations indicates-that the specified calibrations are adequate.
For those devices which employ amplifiers, etc., drift specifications call for drift to be less than 0.4%/ month; i.e., in the period of a month a drift of 0.4% would occur thus providing for-adequate margin.
For the APRM system, drift of electronic apparatus it not the only consideration in determining a calibration frequency.
Chan e in power distribution and loss of chamber sensitivity dictate a calibration every seven days.
Calibration on-this frequency assures _ plant operation at or. below thermal
-limits.
The RPS LOGIt RESPONSE TIME surveillance ensures that the logic response time is less than or equal to the value assumed in the safety analyses.
The logic response time ia measured from the opening of the sensor contact up to and includinti the opening of the trip actuator contacts (de-energization of
- the SCRAM pilot valve solenoids).
The RPS LOGIC RESPONSE TIME acceptance criterion is 50 milliseconds.- RPS LOGIC RESPONSE TIME tests are conducted at least every OPERATING CYCLE. This frequency is consistent with the Millstone refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not chanrel failure, are extremely unlikely.
B. - The peak heat flu.#shall be checked once per day to detemine if the
-APRM scria requires adjustment. This will normally be done by checking the LPRM readings. Only a small number of control rods are moved daily, thus the peaking factors are not expected to change significantly and a daily check of the peak heat flux is adequate.
Millstone Unit 1-3 3/4 1-9 Amendment No. 102
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