ML19224A353
| ML19224A353 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/15/1978 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19224A352 | List: |
| References | |
| TASK-TF, TASK-TMR TM-0167, TM-167, NUDOCS 7901020167 | |
| Download: ML19224A353 (4) | |
Text
ML TRUPULIT AN LUISUN C0fd'ANY JLkSt Y U NIRAL P0hlk & Llull Luf4'ANY PLfitiSYL VANI A LLLCIRIC CUfl'ANY DOCKET No. 50-320 THRLE fille ISLAND NUCLLAR STATION, UNIT 2 Atlhu t,L N i TO F ACILliY UPERATING LICLNSL
/mienU"ent ho. 4 L icense No. UFR-/3 1.
The Nuclear Regulatory Comnission (the Comnission) has found tlat:
A.
The issuance of this license arnendment t.omplies with the standards dnd requirelbents of the AtolhiC [nergy ACt of 1954, as ar.: ended (the Act) and the Coniission's rules and regulations set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Comnission; C.
There is reasonable assurance (i) that the activities authorized by this a:uendment can be conducted without endahgering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comnission's regulations; U.
The issuance of this amendc.ent will not be inimical to the cocmon defense and security or to the health and safety of the public; and E.
The issuance of this aciendment is in accordance with 10 CFR Part 51 of the Comaission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the er, ended f acility Operating License No. UPR-73 is hereby ainended by changing the Technical Specifications as indicated in the attachmuit to this license amendment.
Paragraph 2.C.(2) of an. ended Facility Operating License No. DPR-73 is hereoy amended to read as follows:
790102 o/6 7
. "2.C. (2 ) Technical Specifigions The Technical Specifications contained in Appendices A and B, as revised through An,endirent tio. 8 are hereby incorporated in the license. Metropolitan Edison Coinpany shall operate the f acility in accordance with the Technical Soetifications."
3.
lhis license an;endn:ent is effective as of the date of its issuance.
FOR THE fiUCLEAR REGULATORY CC'EISSION I
>l f
-t k. art *a, Cri f S
t Light Water Reactors Branch No. 4 Division of Project Manaseinent Attachment :
Chanbes to the Technical Specifications Date of issuance:
December 15, 1978 O
POWER DISTRIBUTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNS related parameters shall be maintained within the limits shown on Table 3.2-2:
a.
Reactor Coolant Hot Leg Temperature.
b.
Reactor Coolant Pressure.
c.
Reactor Coolant Flow Rate.
APPLICABILITY: MODE 1.
ACTION:
With any of the above parameters exceeding its limit, restore l a.
the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
With THERMAL POWER limited by the reactor coolant flow rate per Table 3.2-2, reduce the Reactor Protection System Nuclear Overpower trip setpoint per Table 3.2-2 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-2 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.2.5.2 The Reactar Coolant System total flow rate shall be determined to be within its limit by measurement at least once per 18 months.
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TABLE 3.2-2
]
3
,c E
DNB MARGIN P
LIMITS E
o Four Reactor Three Reactor One Reactor Coolant Pumps Coolant Pumps Coolant Pump E
Parameter Operating Operating Operating in Each Loop 2
Reactor Ccolant Hot Leg
< 609.3(j)
< 609.3 m
Temperature, T F
< 609.3 H
II)
Reactor Coolant Pressure, psig(2)
> 2060.4
> 2356.4
> 2091.4
> 250,400
> 182,800 Reactor Coolant Flow Rate, gpm a.
> 370,496 with I) w1 THERMAL POWER < 2717 MW m
b.
> 373,120 with 2744 MW '(4) 2717 MWt < THERMAL POWER 1 t
c.
> 377,000 with 2744 MW < THERMAL POWER 1 2772 MW t
{
U } Applicable to the loop with 2 Reactur Coolant Pumps Operating.
2 (2) Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of E
RATED THERMAL POWER per minute or a THEPFAL POWER step increase of greater than 10%
of RATED THERMAL POWER.
zo IIThe Nuclear Cverpower trip setpoint shall be reduced to 1 103.5% of RATED THERMAL POWER.
I The Nuclear Overpower trip setpoint shall be reduced to 1 104.5% of RATED THERMAL POWER.
I