ML20082P277
| ML20082P277 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/22/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20082P280 | List: |
| References | |
| DPR-35-A-072 NUDOCS 8312080173 | |
| Download: ML20082P277 (11) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPER'ATING LICENSE Amendment No. 72 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Boston Edison Company (the licensee)datedMay 31, 1983 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 appl'ication, 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:
l B.
Technical Specifications l
The Technical Specifications contained in Appendix A, as revised j
through Amendinent No. 72, are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the Technical Specifications.
8312080173 831122 PDR ADOCK 05000293 P
PDR l
s 2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUC EAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licen. sing I
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 22, 1983 9
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e ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
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1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 1.1 FML CIAIBING INTEGRITY 2.1 FUEL CIADDING INTEGRITY Applicability:
Applicability:
Applies to the interrelated variables associated with fuel Applies to trip settings of the instruments and devices which are thermal behavior.
- provided to prevent the reactor system safety limits from being exceeded.
Objective:
Objective:
To establish limits below which To define the level of the pro-the integrity of the fuel clad-ding is preserved.
cess variables at which automatic protective action is initiated to prevent the fuel cladding inte-grity safety limits from being exceeded.
Specification:
Specification:
A.
Reactor Pressure >S00 psia and A.
Neutron Flux Scram Core Flow >101 ef Rated The existence of a minhun=
critical power ratio (MCPR)
The limiting safety system trip settings shall be as specified less than 1.07 shall.consti-below:
tute violation of th'e fuel cladding integrity safety 1.
Neutron Flux Trip Settinas limit. A NCPR of 1.07 is here-inafter referred to as the a.
APRM Flux Scram Trip Safety Limit MCPR.
Settina (Run Mode) 3.
Core Thermal Power Limit (Reac-h a the Mode Switch is tor Pressure 5800 psia and/or Core Flow 5101) in the RUN position, the APRM flux scram k n the reactor pressure is trip setting shall be:
5 800 psia or core flow is less S 5.58W + 62% 2 loop than or equal to 10% of rated, the steady state core thermal Where:
power shall not exceed 25% of design thermal power.
S=
Setting in percent i
of rated thermal C.
Power Transient power (1998 MWt)
The safety limit shall be as-W=
Percent of drive samed to be exceeded when scram flow to produce a is known to have been accomplished rated core flow of by a means other than the expected 69 M lb/hr.
scram signal unless analyses demon-strate that the fuel cladding integrity safety limits defined in Specifications 1.1A and 1.13 were not exceeded during the actual transient.
i Amendment No. k, 72 6
i 1.1 SAFETY LIMIT 2.1 LIMITING SAFETT STSTEM SETTING D.
Menever the reactor is in the In the event of operation with a cold shutdown condition with maximum fraction of limiting power
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irradiated fuel in the reactor density (NFLPD) greater than the vessel, the water level shall fraction of rated power (FRP), the not be less than 12 in. above setting shall be modified as the top of the normal active follows:
fuel zone.
ygp S 5 (0.56W + 62%)
M 2 Loop
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Where.
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FRP = fraction of rated thermal power (1998 MWt)
MFLPD = maximum fraction of limit-ing power density where the limiting power density is 13.4 KW/ft for 8x8 and P8x8R fuel.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
For no combination of loop recire-ulation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power.
b.
APRM Flux Scram Trip Settina (Refuel or Start and Hot Standby Mode)
When the reactor mode switch is in the REFUEL or STARTUP position, the APRM scram shall be set at less than or equal'to 15% of rated power.
c.
IRM The IRM flux scram setting shall be 5120/125 of scale.
B.
APRM Rod Block Trip Settina The APRM rod block trip setting shall be:
S 1 0.58W + 50% 2 Loop g
A.
1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING
- Mare, IRR = Rod block setting in per-cent of rated thermal power (1998 MWt)
W = Percent of drive flow re-quired to produce a rated core flow of 69M lb/hr.
In the event of operating with a assimum fraction limiting power density (NFLPD) greater than the fraction of rated power (FRP),
the setting shall be modified as follows:
FRP S
5 (O. 58W + 50%)
EEUD 2 Loop RB
- Where, FRP = fraction of rated thermal power MFLPD = maximum fraction of limit-ing power density where the limiting power density is 13.4 IW/ft for 8x8 and P8x8R fuel.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less I
than the design value of 1.0, in which case the actual operating value will-be used.
C.
Reactor low water level scram setting shall be 2 9 in. on level instruments.
D.
Turbine stop valve clo.ture scram settings shall be 510 percent valve closvea.
E.
Turbine control valve fast clo-sure setting shall be2150 psig control oil pressure at accele-ration relay.
F.
Condenser low vacuum scram set-ting shall be 2 23 in. Hg. vacuum.
G.
Main steam isolation scram setting; shall be i l~0 percent valve closure.
Amendment No.
d, 72
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- 2 Idhen in the refuel or startup/ hot standbv lE modes, the APRf1 scram shall be set at 6 15% of design power
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100 120 =
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APRM Scram and Rod Block Trip Limiting Safety System Settings
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2.1' BASES:
In summary:
- 1. h abnormal operational transients were analyzed to a power level of 1998 Wt.
ii. h licensed maximum power level is 1898 MWt.
iii. Analyses of transients amploy adequately conservative values of the controlling reactor parameters.
iv. h analytical procedures now used result in a more logical answer than the alternative method of assuming a higher starting power in conjunction with the expected values for the parameters.
& bases for individual set points.tre discussed below:
1 A.
Neutron Flux Scram Trip Settinas APRM h average power range monitoring (APRM) syst.em, which is cali-i l
brated using heat balance data taken during steady-state conditions, l.
reads in percent of design power (1998 MWt). Because fission cham-bers provide the basic input signals, the APRM system responds directly to average neutron fluz.
Durint transients, the instan-taneous rate of. heat transfer from the fuel (reactor thermal power) l is less than the instantaneous neutron flux due to the time constant of the fuel.
Therefore, during abnormal operational transients, the thermal power of the fuel vill be less than that indicated by the neutron flux at the scram setting. Analyses demonstrated that with a 120 percent scram trip setting, sone of the abnormal operational transients analyzed violate the fuel safety limit and there is a substantial margin from fuel damage.
Therefore, the use of flow referenced scram trip provides even additional margin.
The flow biased scram plotted on Figure 2.1.1 is based on recircula-l
)
tion loop flow.
An increase in the APRM scram setting would decrease the margin pre-sent before the fuel cladding integrity safety limit is reached.
h AFRN scram setting was determined by an analysis of margins re-geired to provide a reasonable rtage for maneuvering during opera-i tion.
Reducing this operating margin would increase the frequency of spurious scrams, ubich have an adverse effect on reactor safety because of the resulting thermal stresses.
Thus, the APRM setting ass selected because it provides adquate margin for the fuel clad-ding integrity safety limit yet allows operating margin that reduces the possibility of unnecessary scrams.
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AmendmnR Na.1/, 72
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FNPS TABLE 3.2.C IRSTRt20!NTATION THAT INITIATES ROD BLOCES f
Minimum # of Operable Instrument Chamaels Per Trip Systems (1)
Instrument Trip Invel Settina 5
4 2
APRM Upscale (Flow (0.58W + 50%)
FRP (2)
Blased)
MFLPD 2
APRM Dowaacale 2.5 indicated on scale I (7)
Rod Block Monitor (0.65W + 42%)
FRP (2)
(Flow Biased)
MFl.PD 1 (7)
Rod Block Monitor 5/125 of full scale Downscale
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3 IRM Downscale (3) 5/125 of full scale 3
IRM Detector not in (8)
Startup Position 3
IRM Upscale 5108/125 of full scale t
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2 (5)
SRM Detector not in (4)
Startup Position 2 (5) (6)
SRM Upscale
- 510 counts /sec.
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Scram Discharse Volume 518 gallons Water Level-Nigh l
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l Amendment No.
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