ML20078K515
| ML20078K515 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/17/1994 |
| From: | Larry Wheeler Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078K519 | List: |
| References | |
| NUDOCS 9411230112 | |
| Download: ML20078K515 (12) | |
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WASHINGTON,0, C. 20555 DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter !;
8.
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 set forth in 10 CFR Chapter I; 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.
9411230112 941117 PDR ADOCK 05000369 P
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NnF-9 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 152 are hereby incorporated into thic 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
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Louis L. Wheeler, Acting Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 17. 1994
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UNITED STATES i,
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DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NVCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found'that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the' Commission's rules and regulations as set forth in 10 CCR Chapter I; 8.
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 sucn activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; r
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 l
been satisfied.
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. e 2.
Accordingly, the license is hereby amended by page changes to the Technical-Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-17 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 134, are hereby ir.:arporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
1 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance, i -
FOR THE NUCLEAR REGULATORY COMMISSION S
s j aus Louis L. Wheeler, Acting Director Project Directorate II-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 17, 1994
ATTACHMENT TO LICENSE AMEN 0 MENT NO.152 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET N0. 50-369 AND TO LICENSE AMENDMENT NO 134 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised paces are identified by Amendment number and contain vertical lines indicating
, areas of change.
Remove Paaes Insert Paaes 3/4 1-9 3/4 1-9 3/4 1-10 3/4 1/10 3/4 5-9 3/4 5-9 8 3/4 1-3 8 3/4 1-3, B 3/4 1-4 8 3/4 1-4 8 3/4 5-2 8 3/4 5-2, B 3/4 5-3 8 3/4 5-3
'No change - overflow page 4
REACTIVITY CONTROL SYSTEMS CHARG_l!1G PUMP - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 One" charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of Leing powered from an OPERABLE emergency power source.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no charging pump OPI'RABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
i SURVEILLANCE RE0VIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying a differential pressure across the pump of greater than or equal to 2380 psid is developed when tested pursuant to Specification 4.0.5.
4.1.2.3.2 All centrifugal charging pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable at least once per 31 days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position or by verifying the discharge of each charging pump has been isolated from the Reactor Coolant System by at least two isolation valves with power removed from the valve operators.
"Two charging pumps may be operable and operating for $15 minutes to allow swapping charging pumps.
l i
McGUIRE - UNITS I and 2 3/4 1-9 Amendment No. 152 (Unit 1)
Amendment No.134 (Unit 2) i
REACTIVITY CONTROL SYSTEMS
[HARGING PUMPS - OPERATING LIMITING CONDITION FO OPERATION 3.1.2.4 At least two# rharging pumps shall be OPERA 8LE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% delta k/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 at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying a differential pressure across each pump of greater than or equal to 2380 psid is developed when tested pursuant to Specification 4.0.5.
the above required OPERABLE 4.1.2.4.2 All centrifugal charging pumps pump, shall be demonstrated inoperable at once per 31 days whenever the temperature of one or more of the RCS cold.egs is less than or equal to 300*F by verifying that the motor circuit breakers are secured in the open. position or by verifying the discharge of each charging pump has been isolated from the Reactor Coolant System by at least two isolation valves with power removed from the valve operators.
- A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 300*F.
Two charging pumps may be operable and operating for $15 minutes to allow swapping charging pumps.
McGUIRE - UNITS 1 and 2 3/4 1-10 Amendment No.152 (Unit 1)
Amendment Nc 134 (Unit 2)
-l 3/4.5.3 ECCS SUBSYSTEMS - Tava F 350*F j
LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
One OPERABLE centrifugal charging pump,#
b.
One OPERABLE RHR heat exchanger, c.
An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of l
operation.
612LICABILITT: MODE 4.
ACTION:
a.
With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the "ow path from the refueling water storage tank, restore at least one ECCS subsystem 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 COLD SHUTOOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
i b.
With no ECCS subsystem OPERABLE because of the inoperability of either the RHR heat exchanger or RHR pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T
less than 350*F by use of alternate heat removal methods.
m c.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumu-lated actuation cycles to date.
The current value of the usage fac-tar for each affected Safety Injection nozzle shall be p; ided in this Special Report whenever its value exceeds 0.70.
- A maximum of one centrifugal charging pump and one Safety Injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold 1
legs is less than or equal to 300*F.
Two charging ;: umps may be operable and operating for s15 minutes to allow swapping charging pumps.
McGUIRE - UNIT 1 and 2 3/4 5-9 Amendment No. 152 (Unit 1)
Amendment 16. 134 (Unit 2)
REAC' TY CONTROL SYSTEMS BASES B0 RATION SYSTEMS (Continued)
Refuelina Water Storace Tank Reauirements for Maintainina SDM - Modes 1-4 Required volume for maintaining SOM presented in the COLR Unusable volume (below nozzle) 16,000 gallons Additional margin 17,893 gallons With the RCS temperature below 200*F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron injection System becomes inoperable.
The limitation 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.
Allowing two Centrifugt.1 Charging pumps to operate simultaneously for
$15 minutes increases the margin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted during pump swap.
For the 15 minute period during which simultaneous Centrifugal Charging pump operation is allowed, the safety margins as related to the mass addition analysis are not appreciably reduced.
Technical Specification 3.4.9.3 requires two PORVs to be operable during this period of operation, thus a mass addition transient can be relieved as required assuming the two PORVs function properly.
The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1% delta k/k after xenon decay and cooldown from 200*F to 140*F. The minimum borated water volumes and concentrations required to maintain shutdown margin for the Boric Acid Storage System and the Refueling Water Storage Tank are presented in the Core Operating Limits Report.
The Technical Specification LC0 value for the Boric Acid Storage Tank and the Refueling Water Storage Tank minimum contained water volume during Modes 5 and 6 is based on the required volume to maintain shutdown margin, an allowance for unusable volume and additional margin as follows:
Boric Acid Storaae i,nk Reouirements for Maintainino SDM - Modes 5 & 6 Required volume for maintaining SDM presented in the COLR Unusable volume (to maintain full suction pipe) 4,132 gallons Additional margin 1,415 gallons Refuelina Water Storaae Tank Reouirements for Maintainina SDM - Modes 5 & 6 Required volume for maintaining SDM presented in the COLR Unusable volume (below nozzle) 16,000 gallons Additional margin 6,500 gallons McGUIRE - UNITS 1 and 2 8 3/4 1-3 Amendment No. 152 (Unit 1)
Amendment No. 134 (Unit 2)
REACTIVITY CONTROL SYSTEMS BASES
.B.0 RATION SYSTEMS (Continued)
The contained water volume limits include allowance for water not avail-able because of discharge line location and other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1,3 MOVABLE CONTROL ASSEMBLliji The specifications of this section ensure that:
(1) acceptable power dis-tribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of rod misalignment on associated accident anal-yses are limited.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
The control rod insertion limit and shutdown rod insertion limits are specified in the CORE OPERATING LIMITS REPORT per specification 6.9.1.9.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.
Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER.
These restrictions provide assurance of fuel rod integrity during continued operation.
In addi-tion, those safety analyses affected by a misaligned rod are reevaluated to confirm that the resgits remain valid during future operation.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with Tm greater than or equal to 551*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times exper ienced during a Reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more fre-quent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LC0's are satisfied.
For Specification 3.1.3.1 ACTIONS c. and d.,
it is incumbent upon the plant personnel to verify the trippability of the inoperable control rod (s).
This may be by verification of a control system failure, usually electrical in nature, or that the failure is associated with the control rod stepping mechanism.
McGUIRE - UNITS I and 2 8 3/4 1-4 Amendment No. 152 (Unit 1)
Amendment No. 134 (Unit 2)
EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems ensures that suf ficient 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 from the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long-term core cooling capab'ility in the recirculation mode
.iur*'ng 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.
The limitation for a maximum of one centrifugal charging pump and one Safety Injection pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and Safety Injection pumps except the required OPERABLE charging 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.
Allowing two Centrifugal Charging pumps to operate simultaneously for $15 minutes increases the margin of safety with respect to the Reactor Coolant pump seal failure resulting in a LOCA in that the Reactor Coolant pump seal injection flow is not interrupted during pump swap.
For the 15 minute period during which simultaneous Centrifugal Charging pump operation is allowed, the safety margins as related to the mass addition analysis are not appreciably reduced.
Technical Specification 3.4.9.3 requires two PORVs to be operable during this period of operation, thus a mass addition transient can be relieved as required assuming the two PORVs function properly.
The Surveillance Requirements provided to ensure OPERABILITY of each com-ponent ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
Surveillance Require-ments for throttle valve position stops and flow balance testing provide assur-ance that proper ECCS flows will be maintained in the event of a LOCA. Main-tenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceed-ing runout conditions when the system is in its minimum resistance configura-tion, (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
[ Deleted]
4 4
McGUIRE - UNITS 1 AND 2 B 3/4 5-2 Amendment No. 152 (Unit 1)
Amendment No. 134 (Unit 2)
I fMERGENCY CORE C00UNG SYSTEMS BASES REFUELING WATER STORAGE TANK (Continued) 3/4.5.5 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injec-tion 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 subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all contrr rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location c other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
't McGUIRE - UNITS 1 AND 2 B 3/4 5-3 Amendment No.152 (Unit 1)
Amendment No.134 (Unit 2)