ML20093F306
| ML20093F306 | |
| Person / Time | |
|---|---|
| Site: | Monticello  (DPR-022) |
| Issue date: | 09/24/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20093F310 | List: |
| References | |
| DPR-22-A-026 NUDOCS 8410150049 | |
| Download: ML20093F306 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3 j-J WASHINGTON, D. C,20555
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 L'icense No. DPR-22
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The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated April 2,1984, supplemented by the General Electric Company's document #23A1673 dated January 1984, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the
. Comission; C.
There is reasonable assurance.(i) that the activities. authorized by this amendment can be conducted without endangering the health an sefety of the public and (ii) that such activities will be conducted in compliance with the Comissign's regulations; D.
The issuance of this amendment will not be inimical to the comon
' 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 Comission'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-22 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amandment No. 26, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8410150049 840924 DR ADOCK 0500026]
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Domenic B. Vassallo, Chief-Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Tec):nical
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Specifications Date of Issuance:
September 24, 1984 r
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ATTACHMENT TO LICENSE AMENDMENT fl0. 26 FACILITY OPERATING LICENSE NO. DPR-22
- DOCKET NO. 50-263 Remove the following pages and insert identically numbered pages:
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{i Bases 3.4 and 4.4:
A. The design objective of the standby liquid control system is to provide the capability of bringing the
{2 reactor from full power to a cold, xenon-free shutdown assuming'that none of the withdrawn control rods l,o can be inserted.
To meet this objective, the liquid control system is' designed to inject a quantity of boron which produces a concentration of 660 ppe of boron in the reactor core in less than 125 y
im minutes. The 660 ppm boron concentration in the reactor core is required to' bring the reactor from full power 'to a 3% A P suberitical condition considering the hot to cold reactivity swing, xenon 1
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poisoning and an additional 25% boron concentration margin for possible imperfect mixing of the chemical solution in the reactor water and dilution from the water in the cooldown circuit.
A minimum net quantity of 1400 gallons of solution having a 21.4% sodium pentaborate concentration is required to j
meet this shutdown requirement.
The time requirement (125 minutes) for insertion of the boron solution was selected to override the rate of reactivity insertion due to cooldown of the reactor following.the xenon poison peak.
The i
maximum net storage volume of the boron solution is 2895 gallons.
(256 gallons are contained below the pump suction and, therefore, have not been used in the net quantities above.)
Boron concentration, solution temperature, and volume (including check of tank heater and pipe heat t
tracing system) are checked on a frequency to assure a high reliability of operation of the system should it ever be required.
Experience with pump operability demonstrates that testing at a three-month interval is adequate to detect if failures have occurred.
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The only practical time to test the standby liquid control system is during a refueling outage and by
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i initiation from local stations.
Components of the system are checked periodically as described above and make a functional test of the entire, system on a frequency of less than once each refueling outage unnecessary. A test of explosive charges from one manufacturiag batch is made to assure that the replacement charges for the tested system are satisfactory.
A continual check of the firing circuit continuity is provided by pilot lights in the control room.
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The relief valves in the standby liquid control system protect the system piping and positive dis-
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placement pumps which. re nominally designed for 1500 psi from overpressure.
The pressure relief valves discharge back to the standby liquid control solution tank.
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3.4/4.4 BASES 99 REV i
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS-3.11 REACTOR FUEL ASSEMBLIES 4.11 REACTOR FUEL ASSEMBLIES 1
Applicability
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Applicability-The Limiting Conditions for Operation associated The Surveillance Requirements apply to I
with the fuel rods apply to those parameters the parameters which monitor the fuel which monitor. the fuel rod operating conditions.
rod operating conditions.
i Objective Objective i
j The objective of the Limiting Conditions for Opera-The objective of the Surveillance Require-1 j
tion
's to assure the performance of the fuel rods.
ments is to specify the type.and frequency l
of surveillance to be applied to the fuel rods.
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S pecifica tions Specifications 1
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A. Average Planar Linear Heat Generation Rate (APLHGR)
A. Average Planar Linear Heat Genera-p tion Rate (APLHGR) j During power operation, the APLHCR for each j
type of fuel as a function of average planar The APLHCR for each type of fuel as i
exposure shall not exceed the limiting value a function of average planar exposure 3
given in Table 3.11.1 hased on a straight shall be determined daily during line interpolation between data points.
When reactor operation at > 25% rated core flow is less than 90% of rated core flow, thermal power.
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the APLHGR shall not exceed 94% of the limit-ing value given in Table 3.11.1.
When core j
flow is less than 70% of rated core flow, l
the APLHCR shall not exceed 91% of the lintt-J lag value given in Table 3.11.1.
If any i
time during operation it is determined
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that the limit for APLHGR is being ex-l ceeded, action shall be initiated within 15 1
j 3.11/4.11 211 1
REV
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9 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS C. Minimum Critical Power Ratio (MCPR)
C. Minimum Critical Power Ratio (MCPR)
During power operation the Operating MCPR Limit MCPR shall be determined daily during l
shall be > 1.35 for 8x8, > 1.38 for P8x8R reactor power operation at > 25% rated fuel at rited power and ' flow, provided thermal power and following any change (see section 3'.3.C.3).
If at any.
in power level or distribution which has T3>T tind du"r"i*ng operation it is determined that the the potential of bringing the core to its limiting value for MCPR is being exceeded, action operating HCPR Limit, shall be initiated within 15 minutes to restore operation to within the prescribed limits.
Surveil-lance and corresponding action shall continue until reactor operations is within the prescribed limits.
If the steady state MCPR is not returned to within the prescribed limits within two (2) hours, the '
reactor shall be brought to the Cold Shutdown con-dition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
For core flows other than '
rated the Operating MCPR Limit shall be the above applicable MCPR value time K where K is as shown g
g in Figure 3.11.3.
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CIf Tave > T
, the operating HCPR Limit shall be a linear B
interpolation between the limits in 3.11.C and 1.43 for 8x8, and 1.45 for P8x8R.
3.11/4.11 213 REV
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