ML20066L251
| ML20066L251 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/10/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20066L254 | List: |
| References | |
| DPR-35-A-065 NUDOCS 8211300110 | |
| Download: ML20066L251 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5
- E WASHINGTCN, D. C. 20555 g
49 BOSTON EDISON COMPANY DOCKET NO. 50-293
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PILGRIM NUCLEAR POWER STATION AMENDMENT,,TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A..t The application for amendment by Boston Edison Company (the '
licensee) dated Aucust 3.0, 1982 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 confomity with the applicatio'n, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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;
'D.
The issuance of this acendment 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No' DPR-35 is hereby amended to read as follows:
3 B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8211300110 821110 i
PDR ADOCK 05000293 P
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 10, 1982 e
y
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ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove Insert i
1 54 54 55 55 63 63 84 84 85 85 86 86 O
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.8 TABLE OF CONTENTS Fame No.
1-1.0 DEFINITIONS SATETY LIMITS LIMITING SATETY SYSTE4 SETTINGS 1.1 FUEL CLADDING INTECRITT 2.1 6
1.2 REACTOR COOLANT SYSTS INTEGRITY 2.2 22 LIMITINO C0tiDITIONS FOR OPERATION SURVIILIANCE REQUIRDTIT 3.1 RT. ACTOR PROTECTION SYSim 4.1 26
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4.2 42 3.2 PROTECTIVE INSTRUMENTATION 4.3 80 3.3 REACTIVITY CONTROL
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A 80 A.
Reactivity Limitations 81 3
3.
Control Rods 33 C
C.
Scram Insertion Times D
84 D.
85 E.
Reactivity Anomalies 85 T.
Alternate Require =ents G.
85 4.4 95 3.4 STANDBY LIQU*D CONTROL SYSTIM A
95 A.
Nornal System Availability 96 B
3.
Operation with Inoperable Components 97 C
C.
Sodium Pentaborate Solution 97 D.
Alternate Requirements 3.5 CORE AND CONTAINMEh"I COOLING SYSTIMS 4.5 103 A
103 A.
Core Spray and LPC1 Subsystems 106 B
3.
Containment' Cooling Subsystem 107 C
C.
HPCI Subsystem 108 D
D.
RCIC Subsystem 109 E
E.
Automatic Depressurization System T.
Minimum'Lov Pressure Cooling System and 110 Diesel Generator Availability T
111 C
C. (Deleted) 112 E.
Maintenance of Filled Discharge Pipe R
4.6 123 3.6 FRIMARY SYST E BOUNDAIT 123 A
A.
Thermal and Pressurization Limitations 124 3
3.
Coolant Chemistry 125 C
C.
Coolant Leakage 126 D
D.
Saf ety and Relief Valves 127 E
E.
Jet Pumps 127 T
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7.
Jet Pump Flow Mismatch 127 C
G.
Structural Integrity 1275 B.
Righ Energy Pipina /Outside Containment) H 137a I
1.
Shock Suppresi. ors (Soubbers) i Amendment No. 65 un
e c,
I FMPS TABLE 3.2.C 1HSTMMENTATION 11 TAT IHtTI ATES 300 SLOCKS sa y
4 Hi.
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. Chesnels rer Trip Systems (t)
D,er.u.
..tr, e.t Trip I.evel setting instrument E
APAM Upecele (Flow (0.65W + 42)
"~ rar" (2) 2
.HFLPH missed)
AFRH Downecate 2.5 indicated om ecele 2
Rod Block Monitor (0.65W + 42)
~ FAP _"
(2) t (7)
JFl.PD.
(Flow Blased)
Rod Block Honttor 5/125 of fult scate 1 (7)
I Downecole 1RH Downecele (3) 5/125 et full scale 3
1RH Detector not in (8) 3 Startup Fooltion l
3 1pH Upeceta 1800/125 of full scele ERM Detector mot in (4) 2 (5)
Startup Fosition 5
2 (5) (6)
SRH Upecele 110 counteleec.
l 1.(9)
-418 gallons Water Level-High i
9 46
i yCT!s 7C1 IA3'! 3.2.c[
Tor the startup and rus positions of the Reactor Mods selector Switch, for asch function.
ths:s shall be tso cperable or tripped trip systa=s 1.
The SM and IM blocks need not be operable is "Run" moda, and the If the AFM and RM rod blocks need not be opetable in "scartup" h t time the tion say exist for up to seven days provided that during t aily thereaf tar; operable system is functionally testad i=mediataly and da If this condition las s longer than savan days, the system sh tripped.
syste=s shall be tripped.
f' W is percent of drive flev required to produca a rated co 2.
I3Lv dev scale is bypassed when it is on its lovast ran'ge.
3.
nis f.:metion is bypassed when the count rats is 1 00 cya.
1 4.
Cza of the four SM imputs may be bypassed.
5.
- his SM function is bypassed whas tha ::M. ranga switches are an 6.
- :ss 8 or above.
na t:1p is bypassed when the reactor povar is $30%.
7.
This function is bypassed when the mode switch is placed in Run.
8.
If the number of operable channels is less than required by the minimum pla +
number of operable instrument channels per trip system requirement, 9.
hour.
the inoperable channel in the tripped condition within one 4
Amendment No. 65 55 e
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cn FMPS TABLE 4.2.C HINI!R'M TEST amu CALIRRATICK FREQUCHCT TUR CONTROL E00 BIECn ACTUATIed 1
Instrument Channel InstriementFuncitonal Calthration Instrument Check Test
- 1) APRM - Dinenscole (1) (3) ence/3 months Onec/ Jay
- 2) APMI - Upscale (1) (3) 0,ce/3 months once/ day
- 3) IRM - L'p sc a le
(?) (3)
Startu;. or Contrcl Shutd%se (2)
- 4) 1RM - Doanscale (2) (3)
Startup er Centrol St.utdown (2)
- 5) anH - Upscale (1) (3)
Once/6 menths Once/d.y
- 6) RAH - Dmenscale
-(l) (3)
Once/6 monthe Once/ day
- 7) SrJI - Upscale (2) (3)
Stortup or Control Sliutelown (2)
,8) SR:4 - Detector Not in Startup Position (2) (3) startup or control sleutdown (2)
- 9) IRM - Detector Not in Startup Foeition (2) (3)
Startup or Control Shutdown I (2) l10) Scram Disclarge Volume Water Level-High Once/3 Honths Refuel N/A Innic System Functional Test (4) (6)
(1) System logic Check Once/6 Months 4
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LIMITING CONDITION FCR OPI"MTIONS SURVETLIANCE RGUIRDdDIT 3 3.C Scram Insertion Time k.3.C Seram Insertion Time 2.-
The average of the scram 2.
At 16 week intervals, 50%
insertion times for the of the control rod drives three fastest control rods shall be tested as in 4 3.C.1 of all groups of four con-so that every 32 weeks all trol rods in a two by two of the control rods shall array shall be no greater have been tested. Whenever than:
50% of the control rod drives hr.ve 1:en sers: tested, an
( Inserte6 Avg. Scram evaluation shall be made to From Fully Insertion provide reasonable assurance Withdrawn Time See, that proper control rod drive perfor=ance is being 10 58 maintained.
30 1 35 50 2.12 90 5 30 3
The saximu= scram inser-tion time for 90% inser-tion of any operable con-trol rod shall not exceed 7 00 seconds.,
D.
Control Rod Accu =ulators
.D.
Control Rod Accurulaters At all reactors operating pres-Onceashift,c$eckthestatus sures, a rod accu =ulator may of the pressure and level alarms #
be inoperable provided that no for each accu =ulator.
other control rod if the nine-rod square ar. ay aroung this rod has a:
1.
2.
Directional control valve electrically diser'med while in a non-fully in-scrted position.
3.
Scram insertion time greater than the maximum permissible insertion time.
If's control rod with an inoperable accumulator is inserted " full-in" and its directional control valves are electrically disarmed, it shall not be considered to have an inoperable 84 accumulator.
I Am:ndment No. 65
e f.IMITIMC CO*.")1710N FOR OPERATION StmVETLIANCE_ REQUIREMENT E.
,Recetivity Anomalies E.
Roseeivity Anomalies The recctivity equivalent of During the startup test pro ren tha difference between the end stcetups following re fuel-actuct critical rod configur-ing outar,es, the critical rod ation and the a=pected con-configurations will be compared figuration during power to the expected configurations operation shall not exceed 11 at selected operating conditions.
A K.
If this limit is exceed-These cor.parisor.s will be used ed, the reactor will be shut as base data for renetivity down until the cause has been monitoring during subsequent determined and correctiva ac-pcver opert tie.n throu-heut the tions have been taken if such fuel cycle. At specific power actions are appropriate.
operating conditions. the critical rod configurr. tion vill be compared to the configuration expected baeed upon appropriately F.
If Specifications 3.3.A corrected past data. This com-through D above cannot be met, parison will be made at least an orderly shutdown shall be every full power month.
initiated and the reae:or shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Specifications 3.3.A through D above do not apply when there is no fuel in the reactor vessel.
G.
The scram discharge l.
The scram, discharge volume volume drain & vent drain and vent valves thall valves shall be operable be verified open at least once per month. Each valve shall whenever more than one operable control rod is be cycled quarterly. These withdrawn.
valves may be closed intermit-tently for testing under 2.
If any of the scram dis-administrative control, charge voltane drain or vent valves are made or 2.
During each refueling outage found inoperable an verify the' scram discharge orderly shutdevn shall be volume drain and vent valves; initiated and the reactor shall be in Cold Shutdown
.a)
Close within 30 seconds within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
after receipt of a reactor scram signal and b) Open when the scram is reser.
1 85 Amendment 65. _
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