ML20245K376
| ML20245K376 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/28/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20245K380 | List: |
| References | |
| NPF-49-A-037 NUDOCS 8907050110 | |
| Download: ML20245K376 (11) | |
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- gk UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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l NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
DOCKET NO. 50-423 i
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
37 License No. NPF-49 I
i 1.
The Nuclear Regulatory Commission (the Comission) has found that:
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1 A.
The application for amendment by Northeast Nuclear Energy Company, I
et al. (the licensee) dated January 24, 1989, complies with the l
l standards and requirements of the Atomic Energy-- Act of 1954, l
as amended (the Act), and the Commission's rules and regulations sat forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the I
Commission; C.
There is reasonable assurance (1) 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, i
D.
The issuance of this amendment will not be inimical to the cosenon 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 Consission's regulations and all applicable requirements have been satisfied.
1 8907050110 890628 PDR ADOCK 05000423 F'
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-2 2.
Accordingly, the license is amerided by changes to thL Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 37
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
The licensee shall operate the facility in accordance with.the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGU TORY COMMISSION hn
. Stolz, Director ro ect Directorate 1sion of Reactor rojects I/II Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 28,1989 1
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4 ATTACWENT TO LICENSE AMENDMENT NO. 37 FACILTIY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
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Remove Insert 3/4 2-9 3/4 2-9 3/4 2-13 3/4 2-13 l
5-5 5-5 6-21 6-21 l
2
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I J
POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued)
RTP 2)
When the F is less than or equal to the F limit for the x
appropriate measured core plane, additional power distribution j
RTP maps shall-be taken and F f compared to F andFhy at least x
x once per 31 EFPD.
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e.
The F limits for RATED THERMAL POWER (FRTP) shall be provided for
)
xy x
all core planes containing Bank "D" control rods and all unrodded l
core planes in a Radial Peaking Factor Limit Report per Specifica tion 6.9.1.6; f.
The F limits of Specification 4.2.2.1.2e., above, are not applica-xy ble in the following core planes regions as measured in percent of core height from the bottom of the fuel:
1)
Lower cc.e region from 0 to 15%, inclusive, l
l 2)
Upper core region from 85 to 100%, inclusive, J
3)
Within 2% of core height ( 2.88 inches) of grid plane regions.
I The total core height eliminated from the grid plane regions i
located between 15% and 85% of core height shall not exceed 20%
of total core height (144 inches).
4 4)
Core plane regions within 2% of core height it 2.88 inches) about the bank demand position of the Bank "D" control rods.
Ffexceeding F f the effects g.
With of F on F (Z) shall be x
x xy g
evaluated to determine if F (Z) is within its limits.
g 4.2.2.1.3 When F (Z) is measured for other than F determinations, an g
xy overall measured F (Z) shall be obtained from a power distribution map and g
increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty, MILLSTONE - UNIT 3 3/4 2-9 Amendment No. 37
1.50 1.25 - -
C 1.00
-o fu 5
0.75 -
".320 2
<I CORE HEIGHT K(Z) bz O.000 1.000 l
a O.50 -
5ON tMo t:!
10.800 0.94 0 12.000 0.647 0.25 - -
O.00 O
2 4
6 8
10 12 I
CORE HEIGHT (FT) i l
l FIGURE 3.2-2a-K(Z) - NORMALIZE 0 F (Z) AS A FUNCTION OF CORE HEIGHT g
FOR FOUR LOOP OPERATION MILLSTONE - UNIT 3 3/4 2-10
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POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued) 65 RTP 2)
When the F is less than or equal to the F limit for the appropriate measured core
- plane, additional power.
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65 RTP distribution maps shall be taken and F compared to F x
and F at least once per 31 EFPD.
xy e.
The F limits for 65% of RATED THERMAL POWER (F 65 RTP) and the F xy xy multiplier (MFxy) shall be provided for alll core planes containing' Bank "D" control rods and all unrodded core planes in 'a Radial' Peaking Factor Limit Report per Specification 6.9.1.6;'
f.
The F limits of Specification 4.2.2.2.2e., above, are not applicable xy in the following core planes regions as measured in percent of core height from the bottom of the fuel:-
1)
Lower core region from 0 to 15%, inclusive, 2)
Upper core region from 85 to 100%, inclusive, 3)
Within 2% of core height ( 2.88 inches) of grid plane regions.
j The total core height eliminated from the grid plane regions s
located between 15% and 85% of core height shall not exceed 20%
of total core height (144 inches).
4)
Core plane regions within 2% of core. height (12.88. inches) about the bank demand position of the Bank "D" control rods.
WithFfexceedingFftheeffectsofF g.
on F (Z) shall-be evaluated x
x xy g
to determine if F (Z) is within its limits.
1 g
4.2.2.2.3 When F (Z) is measured for other than F determinations, an g
xy overall measured F (Z) shall be obtained from a power distribution map r..d g
increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
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MILLSTONE - UNIT 3 3/4 2-13 Amendment No. 37 i
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1.50 l
1.25 -
1.00 a
e 5
0.75 -
T 7" 2.500 2
CORE HEIGHT K(2) 8z O.000 1.000 1
0.50 -
50*
2ON 10.800 0.940 x
12.00O O.577 0.25 -
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i O.00 O
2 4
6 8
10 12 CORE HEIGHT (FT) l l
FIGURE 3.2-2b K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT q
FOR THREE LOOP OPERATION MILLSTONE - UNIT 3
.3/4 2-14
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l DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES l
5.3.1 The core shall contain 193 fuel assemblies with ' each fuel assembly l
containing 264 fuel rod locations.
Fuel rod locations may at any time during plant life have - any combination of,1)' fuel rods clad _with zircaloy-4, 2)
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filler. rods fabricated from zircaloy-4 or stainless steel, or 2) vacancies, as 1-determined by cycle-specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall. have a maximum nominal enrichment cf 3.4 weight percent U-235.
Reload fuel shall be 'similar in physical design-to the ' initial core loading and shall have a maximum nominal enrichment of 5.0 weight percent U-235.
CONTROL R0D ASSEMBLIES i
5.3.2 The core shall contain 61 full-length control rod assemblies.
The full-length control rod assemblies shall contain a. nominal 142 inches of absorber material.
The nominal values of absorber material shall be 95.3%
hafnium'and 4.5% natural zirconium or 80% silver. 15% indium, and 5% cadmium.-
All control rods shall be clad with stainless-steel.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of l
the FSAR, with allowance for normal degradation pursuant to the i
applicable Surveillance Requirements, 1
b.
For a pressure of 2500 psia, and For a temperature of 6508F, except for the pressurizer which is -
c.
6800F.
j VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant -System is 12,240 cubic feet at a nominal T,yg of 5878F.
l 5.5 METEOROLOGICAL TOWER LOCATION i
1 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-3.-
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l MILLSTONE - UNIT 3 5-5 AmendmentNo.)(37.
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DESIGN FEATURES 5.6 FUEt STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance of 2.6%
Ak/k for uncertainties as described in Section 4.3 of the FSAR, and b.
A nominal 20.35-inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.2.2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 45 feet.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 756 PWR fuel assemblies.
5.7 CO@DNENT CYCLIC OR TRANS!ENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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MILLSTONE - UNIT 3 5-6
1 ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.4 Routine Semiannual Radioactive: Effluent Release Reports covering the-operation of the ' unit during the previous 6 months of operation shall: be
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submitted within 60 days after January I and July I of each year.
A supplemental report containing dose assessments for the-previous year shall be submitted annually within 90 days after January 1.
l The report shall include that information delineated in the REMODCM.
Any changes to the REMODCM shall be submitted. in the ' Semiannual Radioactive Effluent Release Report.
MONTHLY OPERATING REPORTS l'
6.9.1.5 Routine reports of operating statistics and shutdown experience shall
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be submitted on a monthly basis to the U.S.. Nuclear Regulatory Commi.ssion, Document. Control Desk,- Washington', D.C.
20555, one ' copy to the - Regional E
Administrator Region I, and one copy to the.NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.
RADIAL PEA QNG FACTOR LIMIT REPORT 6.9.1.6 The F limits for RATED THERMAL POWER (F P) shall be provided to xy the U.S.
Nuclear Regulatory Commission, Document Control Desk Washington, D.C. 20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, for all core planes containing Bank "D" control rods and all unrodded core planes and the plot of ' predicted (Ff.PRel) vs-Axial Core Height with the limit envelope prior to ' each cycle - initial criticality unless otherwise approved by the Commission by letter.
In addition, in the event that the limit should change requiring a new substan-tial or an amended. submittal. to' the Radial Peaking' Factor Limit _ Report, it will be submitted prior to the date the limit would become effective unless otherwise approved by the Commission by letter.
Any information needed to RTP support F will be by request from the NRC and need not be included..in this x
report.
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- A single submittal may be made for a multiple unit station. The submittal'
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should combine those sections that are common to all units at the station; l
however, for units with separate radwaste systems, the submittal shall i
specify the releases of radioactive material from each unit.
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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Comission, Document Control Desk, Washington, D.C.
20555, one copy to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, within the time period specified for each report.
6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.2 The following records shall be retained for. at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level; b.
Records and logs of principal maintenance. activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; c.
All REPORTABLE EVENTS; d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; Records of changes made to the procedures required by e.
Specification 6.8.1; f.
Records of radioactive shipments; g.
Records of sealed source and fission detector leak tests and results; and h.
Records of annual physical inventory of all sealed source material of record.
6.10.3 The fellowing records shall be retained for the duration of the unit Operating License:
Records and drawing changes reflecting unit design modifications a.
made to systems and equipment described in the Final Safety Analysis Report; b.
Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; Records of radiation exposure for all individuals entering c.
radiation control areas; MILLSTONE - UNIT 3 6-11 Amendment No. 24
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