ML17054A707
| ML17054A707 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/01/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054A708 | List: |
| References | |
| DPR-63-A-059 NUDOCS 8405210672 | |
| Download: ML17054A707 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION IVASHINGTON,D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE NILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation dated January 9, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 amendment 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
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(2) Technical S ecifications 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 accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 1, 1984 Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
,,, ',<ll I
ll II ATTACHMENT TO LICENSE AMENDMENT NO. 5g lt FACILITY OPERATING LICENSE NO.
DPR-63 OOCKET NO. 50-220 Revise the Appendix. A,',Technical Specifications by removing and inserting the following pages" lt It I
M I
I It Existing
~Pa e
70 Revised
~Pa e
64a 70 The revised areas are indicated by marginal lines.
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LIHITING CONDITION FOR OPERATION SURVEILLANCE RE(UIREHENT c
Hinimum Critical Power Ratio (HCPR)
During power operation, the HCPR for all 8 x 8 fuel at rated power and flow shall be as shown in the table below:
LIHITING CONDITION FOR OPERATING-HCPR c.
Hinimum Critical Power Ratio (HCPR)
HCPR shall be determined daily during reactor power operation atP 25K rated th'ermal power.
d.
Power-Flow Relationshi Core Average Incremental Limiting
--HCPR~
Compliance with the power flow relationship in Section 3.1.7.d shall be determined daily during reactor operation.
> 1.40 e.
Partial Loo 0 eration EOC minus 2
GWD/ST to EOC minus 1
GWD/ST EOC minus 1
GWD/ST to EOC 0 1.45 0 1.50 Under partial loop operation, surveillance requirements 4.1.7.a,b,c, and d above are app1 icable.
d.
If at any time during power operation it is determined by normal surveillance that these limits are no longer met, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If all the operating HCPRs are not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10K per hour until HCPR is within the prescribed limits.
For core flows other than rated the HCPR limits shall be the limits identified above times Kf where.Kf is as shown in Figure 3.1.7-1.
The power/flow relationship shall not exceed the limiting values shown in Figure 3.1.7.aa.
- These limits shall be determined to be applicable each operating cycle by analyses performed utilizing the ODYN transient code.
Amendment No. 59
BASES FOR 3.1.7 AND 4.1.7 FUEL RODS
~Avera e Planar Linear Heat Generation Rate (ALPHGR)
This specification assures that the peak cladding temperature and the peak local cladding oxidation following the postulated design basis loss-of-coolant accident will not exceed the limits specified in 10CFR50, Appendix K.
The peak cladding temperature following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent secondarily on the rod-to-rod power distribution within an assembly.
Since expected local variations in power distribution within a fuel assembly affect the calculated peak clad temperature by less than
+ 20 F relative to the peak temperature for a typical fuel design, the limit on the average linear heat generation raTe is sufficient to assure that calculated temperatures are within the
- 10CFR50, Appendix K limit.
The limiting value for APLHGR is shown in Figure 3.1.7.
These curves are based on calculations using the models described in References 1, 2, 3, 5, 6 and 13.
The Reference 13 LOCA analysis is sensitive to minimum critical power ratio (MCPR).
In that analysis MCPR values of 1.30 for 5 loop operation and 1.36 for 4 and 3 loop operation, were assumed.
If future transient analyses should yield a MCPR limit below either of these values the Reference 13 LOCA analysis MCPR value would become limiting.
The current MCPR limit is ) 1.40.
Linear Heat Generation Rate (LHGR)
This specification assures that the linear heat generation rate in any rod is less than the design linear heat generation even if fuel pellet densification is postulated (Reference 12).
The LHGR shall be checked daily during reactor operation at ) 25K power to determine if fuel burnup or control rod movement has caused changes in power distribution.
I Minimum Critical Power Ratio (MCPR)
At core thermal power levels less than or equal to 25K, the reactor will be operating at a minimum recirculation pump speed and the moderator void content will be very small.
For all designated control rod patterns which may be employed at this point, operating plant experience and thermal-hydraulic analysis indicated that the resulting MCPR value is in excess of requirements by a considerable margin.
With this low void content, any inadvertent core flow increase would only place operation in a more conservative mode relative to MCPR.
During initial startup testing 70 Amendment No.
59