ML17055B580
| ML17055B580 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  (DPR-63-A-081, DPR-63-A-81) |
| Issue date: | 04/30/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055B582 | List: |
| References | |
| NUDOCS 8605050536 | |
| Download: ML17055B580 (10) | |
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1 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 I
NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE NILE POINT NUCLEAR STATION, IJNIT NO.
1 AMFNDMENT TO.'"FACILITY OPFRATING LICENSE Amendment No.
81 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
I A.
The application for amendment by Niagara Mohawk Power Corporati.on (the licensee) dated December 6, 1985, as supplemented lanuarv 13, 1986, complies with the standards and requirements of the Atomic Fneray Act of 1954, as amended (the Act) and the Commission's rules and regulations set forthIin 10 CFR Chapter I; I
B.
The facility will operateIin conformity with the application, the provisions of the Act, an) the rules and regulations of the Commission; C.
There is reasonable assurance (i> that the activities authorized by this amendment can be conducted without endanqerinq the health and safety of the public,'nd (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance o+ this amendment will not be inimical to the common defense and security or to the health and safety of the public; and I
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regul~tions and all applicable requirements have been satisfied.
C 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated i,n the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is herebv amended to read as follows:
8605050536 860430 FOR ADOCV, 05000220 PDR I
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised
=through Amendment No. 81, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REAULATO Y MISSION Joh A; Zwolinski, Director BWR roiect Directorate b'I Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 30, 1986
ATTACHMENT TO LICENSE AMENDMENT NO.
81 FACILITY OPERATINh LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the identified identified indicating Appendix A Technical Specifications by removing the paqes below and inserting the attached pages.
The revised pages are by the captioned amendment number and contain marginal lines the area of change.
REMOVE 63 69a INSERT 63
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREHENT 3.1.7 FUEL RODS 4.1.7 FUEL PODS b 1I The Limiting Conditions for Operation associated with the fuel rods apply to those parameters which monitor the fuel rod operating conditions.
Objective:
The objective of the Limiting Conditions for Operation is to assure the performance of the fuel rods.
The Surveillance Requirements apply to the pa~ameters which monitor the fuel rod operating conditions.
Objective:
The ohjective of the Surveillance Requirements is to specify the type and frequency of surveillance to be applied to the fuel rods.
a.
Avera e Planar Linear Heat Generation a e 1
a.
Avera e Planar Linear Heat Generation ate During power operation, the APLHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value shown in Figures 3.1.7a, 3.1.7b, 3.1.7c, 3.1.7d, 3.1.7e and 3.1.7f.
If at any time during power operation it is determined by normal surveillance that"the limiting value for APLHGR is being exceeded at any node in the core, action shall be initiated within 15 minutes to restore operation to within the prescribed 1imits.
If the APLHGR at all nodes in the core is not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until APLHGR at all nodes is within the prescribed limits.
The APLHGR for each type of fuel as a
function of average planar exposure shall be determined daily during reactor operation at 425 percent rated thermal power.
Amendment Wo. gg, 81
MAPLHGR LIMITS FOR PBDRB299 10 b
CL e
a a
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Cl E3 4
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>C C3 9.15 9.15 9.15 9.13 9.10 8.67 8.61 8.51 8.20 7.65 LEGEND MAPLHGR 0.
5.
1 0.
1 5.
20.
25.
30.
35.
40.
45.
C AVERAGE PLANAR EXPOSURE (GWD/ST)
Figure 3.1.7f Maximum Allowable Average Planar LHGR Applicable to PBDRB299 and Future Reload Fuel as described in Reference 8.
Amendment Ho N.
81 69a
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