ML20054C402
| ML20054C402 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/31/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20054C403 | List: |
| References | |
| DPR-35-A-059 NUDOCS 8204210003 | |
| Download: ML20054C402 (11) | |
Text
9 o p tar i fg UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
E WASHINGTON, D. C. 20L55
]
BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated January 18, 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 application, 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 l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l
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; l
and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements I
have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in j
accordance with the Technical Specifications.
e204210003jg@g2h3 3
l
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
),L Nb Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 31, 1982 I
1
i ATTACHMENT TO LICENSE' AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 i
Replace the following pages of the Appendix "A" Technical Specifications with identically numbered pages.
205A 205C 205E-1 205E-2 205E-3 205E-4 205E-5 205E-6 j
1 t
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREENTS 3.11 REACTOR FUE ASSMBLT 4.11 REACTOR FLTL ASSEM3LT Applicability
_ Applicability De Li=iting Conditions for Ope ration The surveillance Require =ents associated with the fuel rods apply apply to the parameters which to.those parameters which monitor the the fuel rod operating condi-fuel rod ope, rating conditions.
tions.
O'bj ective Objective The Objective of the Li=iting Condi-The Objective of the Surveil-tiens for Operatien is to assure the lance Require =ents is to perfor=ance of the fuel rods.
specify the type end frequency of surveillance to be applied to the fuel rods.
Specifications Specifications A.
Average Planar Lincar Heat A.
Average Pinnar Linear Heat Generation Rate ( APLEGR)
Generation Rate (APLHGR)
During power operation with both The APLEGR for each type of recirculation pu=ps operating, the fuel as a function of average A?LEGR for each type of fuel as a planar exposure shall be function of average planar exposure deter =ined daily during shall not exceed the applicable reactor eperatien at > 25:
limiting value shown in Figures rated the==al power.
l 3.11-1 through 3.11-6.
The' top curves are applicable for core flow greater than or equal to 90% of rated core flow. When core flow is less than 90% of rated core flew, the lower curves shall be limiting. If at any time during operation it is deter =ined by normal surveillance that the ll=iting value for APLHGR is being exceeded, action shall be initiated within 15 =inutes to re-store operation to within the prescribed limits.
If the A?LEGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdevn conditien with-in 36 hcurs. Surveillance and corresponding action shall centinue until reactor operation is within the prescribed li=its.
l 205A
'Am'endment No.
59 3--.-...a=-._.--...
1blE 3.1M Aversee Flanar Linear Best Cenerstion Rate (APLEGR) following the postulated design basis loss-of-cool re will not exceed the limit specified in the 10 CFR So Appe di ent n.x L The peak cladding te=perature (PCI) following a postulated heat generation rate of all the rods of a fuel asse g
axial location and is only dependent, y
to rod power distribution within an asse=bly. secondarily on the rod te=perature is calculated assuming a UCR for the highest The peak clad povered rod which is equal to or less than the design ~ 2C1 This LHOR ti=es 1.02 is used in the heat-up code along with the exposure dependent steady state gap conductance rod-to-rod local peaking factors.
and The limiting value for APLBCR is this LBCR of the highest povered rod divided by its local peaking factor.
The calculational procedure used to establish the APLHCR 11 it The emergency core cooling systen (ECCS) evalu
=
s s.
are e= ployed to deter =ine the effects of the loss of coolant c
accident (LOCA) in accordance with 10CTR50 and Appendix K are discussed in Reference 1.
SCAT, SATE, REFLCOD, and CEASTE.1he todels are identified as LA.5,
'1he LAS Code calculates the the SCAT code to calculate blevdown beat transfer coe and flevs fro = the various ECC syste=s.The SATE code is used t c ents.
Where appropriate, the output of SAFI is used in the LULOOD code to calculate liquid levels.
The results of these codes are used in the 2ASTE code linear heat generation rates O'.AFLEGR) for each fuel ty i
The significant the present plant input pararneters and the MAPLHCR's for included in Reference _2 fuel types ~ calculated by the.above procedure are l
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Amendment No. 59 205c i
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MAXIMUM AVFRAGE PLANAR IINFAR HFAT GENFRATION RATE
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