ML20066B310
| ML20066B310 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 10/14/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066B312 | List: |
| References | |
| TAC-48049, NUDOCS 8211060540 | |
| Download: ML20066B310 (11) | |
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DUKE POWER COMPANY DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Mendment No.17 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amenduent to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated March 2 and March 9,1982, con-ply with the standards and re of 1954, as amended (the Act)quirements of the Atomic Energy Act and the Conmission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Com-mission; 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The i'ssuance 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 hereby amended by page changes to the Technical Specifications as indicated in tne attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications Yhe Technical Specifications contained in Appendix A, as revised through Mendment No.17, are hereby incorporated into this license.
The licensee ethall noorato the facilitv in acenedaneo uitt tha Tachnien1 9nei fi ent < nne and the Environment al Protectior Pl an.
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This license anendment is effective 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSIDH
' " Original Signed I'y: s Elinor G. Adensam, ghief
-Licensing-Branch-No. 4 Division of Licensing Attachnent:
Technical Specification Changes Date of Issuance: October 14, 1982 l
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ATTACHMENT TO LICENSE AMEN 0HENT NO. 17 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 5-11 3/4 5-12 B3/4 5-2 B3/4 5-1 B3/4 6-2 B3/4 6-1 3/4 6-11 3/4 6-12 I
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM BORON INDECTION TANK LIMITING CONDITION FOR OPERATION 3.5.4.1 The baron injection tank shall be OPERABLE with:
A minimum contained borated water volume of 900 gallons, and a.
b.
Between 2,000 and 4,000 ppm of boron.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With the baron injection tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 1% Ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4.1 The boron injection tank shall be demonstrated OPERABLE by:
Verifying the contained borated water volume at least once per 7 a.
days, and l
b.
Verifying the boron concentration of the water in the tank at least l
once per 7 days.
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McGUIRE - UNIT 1 3/4 5-11 Amendment No. 17 l
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EMERGE! ICY CORE COOLING SYSTEMS THIS PAGE INTENTIONALLY LEFT BLANK h.
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1 McGUIRE - UNIT 1 3/4 5-12 Amendment No. 17
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3/4.5 EMERGENCY CORE COOLING SYSTEMS a
BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each RCS accumulator ensures that a suf ficient volume of borated water will be immediately forced into the reactor core through each of the cold legs from the cold leg injection accumulators and directly into the reactor vessel from the upper head injection accumulators in the event the RCS pressure falls below the pressure of the a.comulators.
This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.
The accumulator power operated isolation valves are considered to be
" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.
In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is
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required.
The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.
If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging f rom the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
With the RCS temperature below 350 F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
McGUIRE - UNIT 1 B 3/4 5-1
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The Ifmitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 300 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABIt_ITY is naintained.
Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to cach injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the boron injection system as part of the ECCS ensures that 4
sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown.
RCS cooldown can be caused by inadvertent depressurization, a loss of-coolant accident or a steam line rupture.
The limits on injection tank minimum contained volume and boron concentration ensure that the assumptions used in the steam line break analysis are met.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
3/4.5.5 REFUELING WATER STORAGE TANK l
The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and boron concentration ensure that
- 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subtritical in the l
cold condition following mixing of the RWST and the RCS water volumes with all l
control rods inserted except for the most reactive control assembly.
These assumptions are consistent with the LOCA analyses.
McGUIRE - UNIT 1 8 3/4 5-2 Amendment No.
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3/4.6 CONTAINMENT SYSTEMS 4
BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
T' 3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P As an added conservatism, the
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measured overall integrated leakage rate is. further limited to less than or parqueh to 0.75 L during performance of the periodic tests to account for
-epescible degrad$ tion of the containment leakage barriers between leakage tests.
' The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions o'n CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provide assurance that l
the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the l
containment structure is prevented from exceeding its design negative pressure i
differential with respect to the outside atmosphere of 1.5 psig and 2) the containment peak pressure does not exceed the design pressure of 15 psig during LOCA conditions.
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McGUIRE - UNIT 1 B 3/4 6-1
CONTAINMENT SYSTEMS BASES INTERNAL PRESSURE (Continued)
The maximum peak pressure expected to be obtained from a LOCA event is 14.5 psig.
The limit of 0.3 psig for initial positive containment pressure will limit the total pressure to 14.8 psig which is less than the design pressure and is consistent with the accident analyses.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that 1) the containment air mass is limited to an initial mass sufficiently low to prevent exceeding the design pressure during LOCA conditions and 2) the ambient air temperature does not exceed that temperature allowable for the continuous duty rating specified for equipment and instrumentation located within containe.ent.
The containment pressure transient is sensitive to the initially contained air mass during a LOCA.
The contained air mass increases with decreasing temperature.
The lower temperature limits of 100 F for the lower compartment, 75 F for the upper compartment, and 60 F when less than or equal to 5% of RATED THERMAL POWER will limit the peak pressure to 11.8 psig, which is less than the containment design pressure of 12 psig.
The upper temperature limit influences the peak accident temperature slightly during a LOCA; however, this limit is based primarily upon equipment protection and anticipated operating
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conditions.
Both the upper and lower temperature limits are consistent with the parameters used in the accident analyses.
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards i
for the life of the facility.
Structural. integrity is required to ensure that the vessel will withstand the maximum pressure of 15 psig in the event of a LOCA.
A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 REACTOR BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contrinment reactor building will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to provide
- 1) protection for the steel vessel from external missiles, 2) radiation shielding in the event of a LOCA, and 3) an annulus surrounding the steel vessel that can be maintained at a negative pressure during accident condi-tions.
A visual inspection is sufficient to demonstrate this capability.
McGUIRE - UNIT 1 B 3/4 6-2 Amendment No. :17
CONTAINMENT 5YSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION
- 3. 6.1. 5 Primary containment average air temperature shall be maintained:
between 75 F* and 100 F in the containment upper compartment, and a.
b.
between 100*F* and 120 F in the containment lower compartment.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the containment average air temperature not conforming to the above limits, restore the air temperature to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.5.1 The primary containment upper compartment average air temperature shall be the weighted average ** of all ambient air temperature monitoring j
stations located in the upper compartment.
As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the following locations:
Location
- a. _ Elev. 826' at the inlet of upper containment ventilation Unit 1 A.
b.
Elev. 826' at the inlet of upper containment ventilation Unit 18.
c.
Elev. 826' at the inlet of upper containment ventilation Unit IC.
d.
Elev. 826' at the inlet of upper containment ventilation Unit 10.
- Lower limit may be reduced to 60 F in MODE 2, 3 and 4.
^^The weighted average is the sum of each temperature multiplied by its respective containment volume fraction.
In the event of inoperable tempera-ture sensor (s), the weighted average shall be taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of service.
I McGUIRE - UNIT 1 3/4 6-11 Amendment No.17
s CONTAINMENT SYSTEMS SURVEILLANCEREQUIREMENTS(Continued) 4.6.1.5.2 The primary containment lower compartment average air temperature shall be the weighted average
- of all ambient air temperature monitoring stations located in the lower compartment.
As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the following locations:
Location a.
Elev. 745' at the inlet of lower containment ventilation Unit lA.
b.
Elev. 745' at the inlet of lower containment ventilation Unit 18.
c.
Elev. 745' at the inlet of lower containment ventilation Unit IC.
d.
Elev. 745' at the inlet of lower containment ventilation Unit ID.
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.a
- The weighted average is the sum of each temperature multiplied by its respective containment volume fraction.
In the event of inoperable tempera-ture sensor (s), the weighted average shall be taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of service.
McGUIRE - UNIT 1 3/4 6-12
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