ML20040C431
| ML20040C431 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/16/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML100430256 | List: |
| References | |
| NUDOCS 8201270635 | |
| Download: ML20040C431 (8) | |
Text
c UNITED STATES
(,
NUCLEAR REGULATORY,COM!.HSSION W ASHINGTON. D.
C. 20555
]
CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
DOCKr.T No. 50-24 INDIAN POINT NUCLT.AR CENERATING UNIT NO. 2 AMD;DMENT TO FACILITY OPERA ING LICENSE Amendment No. 14 License No. DPR-26 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Concolidated Edis'on A.
Co.mpany of New York, Inc. (the licencee) dated July 23, 1975, complies with the standards and requirencnts of the A, tonic Energy Act of 1954, as acenddd (the,Act) and the Commission's rules and regulations set forth in 10 Crn Chapter I; d
B.
The facility will operate.in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; The,r,e is reasonabic assurance (i) that the activities authorized l
C.
l by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitics i
will be conducted in co=pliance with the Commission's regulations; and D.
The issuance of this amen'dment will not be inimical to the -
common defense and security or to the health and safety of the public.
According1j, the license is amended by a change to the Technical 2.
l Specifications as indicated in the attachment to this licence amendnent and Paragraph 2.C.(2) of Facility License No. DPR-26 is hereby amended to read as follows:
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"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license.
The licensee hhR DO 05 0 7
shall operate the facility in accordance with P
PDR the Technical Specifications, as revised by (Wc*wdAhanucJewcafn3Andh @hange _No.11."
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This license amendment is effective as of the date of its issuanca.
FOR THE NUCLEAR REGULATORY C0!OfISSIO:;
f Karl R. Coller, Assistant, Director
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for Operating Reactors Division of'Recctor Licunsing
- Attachrsent:
Change No. 11 to the Technical Specifications Date of Issuance:
December 16, 1975 e
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ATTAC!B!ENT TO ' LICENSE M!ENhlr.HT NO. Ne 1
CHANGE NO. 11 TO THE TECHNICAL SPECIFICATIONS FACILITY OPFR4 TING LICENS1: IHO. DPR-26 DOCYJ:T KO. 50-247f.
1 Rep 3 ace pages 3.8-1.through 3.8-6 with the attached
- revised pages.
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~3.8 RcFUELING Applicabi'l h Applies to operating limitations during refueling operations.
Objective To ensure that no incident could occur during refueling operations that wou3d advercely affect public health and safety.
Speciffc; tion During refueling operations, the f o'llowin g conditionn shall be natisfied:
1.
The cquipnent door and at least one door in cach personnel air lock shall be properly closed.
In addition, et least one isointion 3
vulve shall be operabJe or locked cloced in cach line in ne trating the containnent and
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which'providen a direct path fron containuent u
atmosphere to the outside. *
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Radiation levels in the containment and spent.
I fuel storage areas shall be nonitored contin-l l
uously.
3.
The core s'uberitical neutron flux shall be l
continuously monitored by tha tuo cource 4
range monitors, cach uith continuous
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visual indication in the con f.rol room l
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f and one with audible indication in the i
s containhent'available whenever core geometry l
l is being changed.
When core pcometry in not being changed, at least one source range neutron j
flux uonitor shall be in service.
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,a 4.
At least one residual heat removal pump and heat
.b" operabic.
exchanger shall be 5.
During reactor vessel head removal and while
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load $ng and unloading fuel from the reactor, T,yg chall bc_<t 40* F. and the mininue b oron' concon tration sufficient to maintain the reactor
.suberitical by at least 10% Ak/k.
The rcouired
. boron concentration shall be verified by chemical analysis daily.
6.
. Dire c t coumunication between the con trol.r' om and the o
refueling cavity manipulator cranc shall be availabic whencycr changes in core gcometry.are t a k i n g, p l a c'c.
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7.
If the spe.nt fuel pit contains spent fuel, the spent fuel cask shall not be moved over any region of the spent fuel pit until the cash handling system has 11 I
been reviewed by the Nucicar Regulatory Cournission and found to be acceptable.
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8.
The containment vent and. purge system, includ'ing the radiation mon'ito'rs which initiate isolation,. shall be tes ted and verified t.o be operable immediately prior to refueling operations.
9.-
No movement of fuel in the reactor shall be raade until k-the reactor has been suberitical"for at least ninety l 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
In the evant that more t h au. 'on c region of 3,8-2
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" fuel (72 assemblics or less) is to be discharged from 11 the reactor,those assemblics in excess of one region shall not be discharged before a continuous interval of l.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> has elapsed after shutdown; k
- 10. The minimum water level above the top of the core I
shall be at least 23 feet uh en evc r movement of
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spent fuel is being made.
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- 11. A dead-load test shall be succesc' fully performed on tho' fuel storage refueling building crane before fuel movement begins.
The lo a d a s s ur'ae d by th e
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refueling crane for this, test. must be equal to or greater than the maximum load to be assuned h
by the refueling cranc during th e refueling operation.
A throuhh visual inspec' tion of the refueling crane shall'hc unde after the dead load J
test and prior to fuel h nr.d lin g.
12.
The fuel-handling building charcoal filtration system Eust be opetnting whenever spent fuel c:ovement is being made unless the spent, fuel has had a. continuous
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35-day decay period.
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l 13.
A licensed senior reactor operator shall be at the
. site and designated in ch.arge of the operation whenever i
changes in core geometry are taking place.
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3.8-3
B.
If any of the specified limiting c,onditions for
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refueling is not met, refueling shall cease until the spec,1fied limits are met, and no operations which may increase the reactivity of the core shall.be ma,de.
. Basis The equipment and general procedurec to bb utilized during refueling are discussed in the FSAR.
Detailed inctructions, the above-specified precautions, and the design of the fucle handling equipment incorporating builtein interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would renult in a lazard to pub 31c health and safety.(
Whenever changes are not being made in core geometry, one flux monitor is h.
cufficient. This permita maintenance of the instrumentation.
-- Con tinuo s monitoring of radiation,1cycis (2 above) and neutron flux provides inacJiate 1ndication of an uncafo condition.
The residual heat puup is used to maintain a uni f orm boron concentration.
The shutdown cargin indicated in Part 5 will keep the c o r'e suberitical, even if all control rods were withdrawn from the core.
During refueling, the reactor refueling c.yvity is filled with approximately 350,000 gallons of v'a t e r. f.r om the' refueling water storage tank with a boron concentration of 2000 ppm.
The minimum boron concentration of this water at 1615 ppm boron is sufficient to maintain the reactor suberitical by at least 10% Ak/k in the cold t
shutdo'wn with all rods inserted, and will'also maintain the core suberitical even 11 no control rods were inserted into
f reactor.(2)
Periodic checks of refueling water boron the
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concentration insure the proper shutdown margin.
P ar,t 6 allows the control room operator to inform the manipulator operator of any' impending unhafe condition detceted from the main control board ludicators during fuel movement.
In addition to the above safeguards, interlocks are utilized during refueling to ensure safe hand 31ng.
An i
excess ueight interlock is provided on th e lifting hoist to prevent movement of more than one f uel asscubly at can acconmodate a tine.
The spent fuel tr,c,nsfer mechanism only one fuel assembly at a time, T'h e nincty hours decay time follouing pinnt shutdown and' the 23 feet of water above the top of the core are consistent
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with the assumptions used in the dose calculation for the
.f ue)-hand in g a cciden t. The requirement for the fuel.-
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- handling building charcoal filtra,rion. system to be operating when spent fuel movemeni is being made provides*
added assurance that the offuite doses will be within acceptab3c linits in the event of a fuel-handling l
accident.
The additional month of spent fuel decay time vill provide the same, assurance that the offsite doses are within acceptable limits and therefore the 1
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charcoal.filt ra tion s'ysten would not be requi' red to bc
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operating.
l r The waiting time of 400 houru required following plant
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11 shutdown before unloading the entire.rcactor core assures
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3.8-5 L
that the naximum pool water temperature will be within design k-objectives as stated in the FSAR.
11 The pres ~ence of a licensed senior reactor. operator at the site and designated in charge provides qualified supervision of the refueling operation-during changes in core geometry.
f References (1)
FSAR - Section 9.5.2.
(2)
Fuel Densification - Indian Point Nuclear Cencrating Station Unit No. 2, dated January 1973, Table 3.3.
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3.8-6
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