ML20065M690
| ML20065M690 | |
| Person / Time | |
|---|---|
| Site: | Catawba  (NPF-35-A-082, NPF-35-A-82, NPF-52-A-076, NPF-52-A-76) |
| Issue date: | 11/30/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065M696 | List: |
| References | |
| NUDOCS 9012110169 | |
| Download: ML20065M690 (10) | |
Text
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UNITED sT ATEs
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50 413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc.
(licensees)datedMarch 13, 1990, 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 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 (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 Comission's regulations set forth in 10 CFR Chapter I; 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 applicab'e requirements have been satisfied.
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. Accordingly, the license is hereby traended 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-35 is hereby amended to read as follows:
Technical Specifications The Technical-Specifications contained in Appendix A, as revised through Amendment No. 82, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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qhf David B.-Matthews, Director Project Directorate 11-3 Division of Reactor. Projects-l/l!
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes
-Date of-1ssuance:
November 30,-1990
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nsmNGTON, D. C. 20M NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50 414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING olCENSF 7
Amendment No. 76 License No. NPP-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Cat 6wba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself North Carolina Munici Agency No. I and Piedmont Municipal Power Agency (licensees) pal Power dated March 13, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as 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; 6
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 It
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i D.
The issuance of this amendment will not Le inimical to the comnon 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 $1 of.the Comission's regulations and all applicable requirements have o
been satisfied.
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Accordingly, the license is hereby aiutnded 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-52 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
76, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company 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.
1 FOR THE NUCLEAR REGULATORY COMMISSION W1 David B. Ma'tthews, Director
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Project Directorate !!-3 Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
November 30, 1990 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF 52 DOCKET NO. 50-41.4.-
Rep 1hce'the following sages of the Appendix "A" Technical Specifications with the cr. closed pages... Tie revised pages are identifica by Amendment number and contai.a. vertical lines indict, ting the areas of change.
i Remove-Pages insertPages
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3/4 1-11 3/4 1-11 3/4 1-12 3/4 1.
B 3/4 1 3 B 3/4 1-3 t
B 3/4-1-3a-B 3/4 1-3b i
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REACTIVITY CONTROL SYSTEMS 80 RATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
A Boric Acid Storage System with:
1)
A minimum contained borated water volume of 12,000 gallons, l.
2)
A minimum boron concentration of 7 M 0 ppm, and 3)
A minimum solution temperature of-65'F.
b.
The refueling water. storage tank with:
I 1)
. A minimum contained borated water volume of 45,000 ga'lons, l
2)
.A minimum boron concentration of 2000 ppm, and 3)
A minimum solution temperature of 70*F.
-- APPLICABILITY:
MODES 5 and 6.
ACTION:
l With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1. 2. 5 The above' required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1)
Verifying the boron concentration of the water,
'2) -Verifying the contained borated water volume, and 3)
Verifying the. boric acid storage tank solution temperature when
.i it-is the source of borated water.
l b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the refueling water storage tank temperature when it is the source of borated water and the outside air, temperature is less than 70'F.
CATAWBA'- UNITS 1 & 2 3/4 1-11 Amendment No. 82 (Unit 1)
Amendment No. 76 (Unit 2) e
1 REACTIVITY CONTROL SYSTEMS i
B0 RATED WATER SOURCES - OPERATING i
LIMITING CONDITION FOR CPERATION 3.1.2.6 As a minimum, the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:
a.
A Boric Acid Storage System with:
1)
A minimum contained borated water volume of 22,000 gallons, l
2)
A minimum boron concentration of 7000 ppm, and 3)
A minimum solution temperature of 65'F.
b.
The refueling water storage tank with:
1)
A contained borated water volume of at least 363,513 gallons, 2)
A minimum boron concentration of 2000 ppm, 3)
A minimum solution temperature of 70'F, and i
4)
A maximum solution temperature of 100'F.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
-a.
With the Boric Acid Storage System inoperable and being used as one of the above required borated water sources, restore the system 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 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN 6quivalent.to at least 1% ok/k at 200'F; restore the Boric Acid Storage System to.
OPERABLE status within the next 7 days or be in COLD SHU100WN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With the refueling water storage-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 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 />.
i-i ll CATAWBA - UNITS 1 & 2 3/4 1-12 Amendment No. 82(Unit 1) l Amendment No. 76 (Unit 2)
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RFACTIVITY CMTROL SYSTEMS BASES i
I B0 RATION SYSTEM!: (Continued)
MARGIN from ext ected operating conditions of 1.3% ok/k after xenon decay and cooldown to 200*F.
The maximum expected boration capability requirement occurs at EOL f*om full power equilibrium xenon conditions and requires j
9.851 gallons ot' 7000 ppm borated water from the boric acid storage tanks or 57,107 gallons of 2000 ppm borated water from the refueling water storage tank.
The Technical Specification requires 22,000 gallons of 7000 ppm borated water from the boric acia 13nks to be available in Modes 1-4.
This volume is based on the required volume fee maintaining shutdown margin, unusable volume (to allow for a full suction pipe), instrument error, and additional margin to. account for different cores and conservatism as follows:
Modes 1-4 Boric Acid Tank Required volume for maintaining SDM 9,851 gallons i
5% Additional Margin 496 gallons J
Unusable Volume (to maintain full suction pipe) 7,230 gallons L
14" of water equivalent o
Vortexing (4" of water above top of suction pipe 2,066 gallons Instrumentation Error (Based on Total Loop Acc.
1,550 gallons for 1&2 NV5740 loops) - 2" of water equivalent 21,193 gallons This value is-increased to 22,000 gallons for additional margin.
A similar approach is taken for calculating the required Refueling Water Storage Tank volume:
When the temperature of one or more cold legs drops below 285*F in Mode 4, the potential for-low temperature overpressurization of the reactor vessel makes it necessary to render one charging pump INOPERABLE and at least one safety injection pump INOPERABLE.
The limitation for a maximum of one centrifugal charging' pump to be OPERABLE and the Surveillanca Requirement to verify all charging pumps except the required OPERABLE pur be inoperable below 285 F provides assurance that a mass addition presst
.ansient can be relieved by the operation'of_ a single PORV.
Refuelina Water Storace Tank Requirements For Maintaining SDM - Modes 1-4 Required Volume for Maintaining SDM 57,107 gallons Unusable Volume (below nozzle) 13,442 gallons Instrument Inaccuracy 11,307 gallons Vortexing 13,247 aallons F5,103 gallons 4
The Technical Specification Volume 363,513 gallons was determined by correcting the tank's low level setpoint (level at which makeup is added to I
CATAWBA - UNITS 1&2 B 3/4 1-3 Amendment No. 82(Unit 1) l Amendment No. 76(Unit 2)
REACTIVITY CONTROL SYSTEMS BASES B0 RATION SYSTEMS (Coritinued) tank)for instrument inaccuracy.
This level provides the maximum available vol W to account for shutdown margin, worst case single failure, adequate containment sump volume for transfer to recirculation, and sufficient volume above the switchover initiation level such that no operator action is required prior to ten minutes after the initiation of the accident.
With the coolant temperature below 200 F, one Boron Injection flow path is l
acceptable without sincie 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 flow path becomes inoperable.
The boron capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1% ak/k after xenon decay and cooldown from 200 F to I
140 F.
This condition requires either 585 gallons of 7000 ppm borated water from the boric acid storage tanks or 3500 gallons of 2000 ppm borated water from the refueling water storage tank.
The Boric Acid Tank and Refueling Water Storage Tank volumes required in Modes 5-6 to reovide necessary SOM are based on the following inputs as discussed previously:
Aoric Acid Tank Required Volume for maiaainina SOM 585 gallons Unusable Volume, Vortexing, Inst. Error 10,846 gallons 5% additional cargin 33 gallons 11,464 gallons This value is increased to the Technical Specification value of 12,000 gallons for additional margin.
, Refueling Water Stoyage Tank Required Volume for Maintaining SDM 3,500 gallons Water Below the Nozzle 13,442 gallons Instrument Inaccuracy 11,307 gallons Vortexing 13,247 gallons 41,496 gallons This value is increased to the Technical Specification value of 45,000 gallons for additional margin.
The contained water volume limits include allowance for water not available
(
because of discharge line location and other physical characteristics.
CATAWBA - UNITS 1&2 B 3/4 1-3a Amendment No. 82 (Unit 1)
Amendment No. 76 (Unit 2)
Z
-REACTIVITY CONTROL-SYSTEMS l
BASES BORATION SYSTEMS (Continued)
The limits on contained water volume and boron concentration of the refueling water storage tank also en.ure a pH value of between 8 and 9 l
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 ASSEMBLIES The specifications of this section ensure that:
(1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of rod misalignment on associated accident analyses are limited, OPERABILITY of the control rod position indicators is reqaired to determine control rod positions and thereby ensure-compliance with
.the control rod alignment and insertion limits.
Verification that the Digital Rod Position Indicator agrees with the demanded position within i 12 steps at 24, 48, and 120 steps and fully withdrawn (> 225 steps) for the Control Banks and 18 and 210 steps and fully withdrawn for the Shutdown Banks provides assurances-that the Digital Rod Position Indicator is operating correctly over the full range of-indication.
Since the Digital-Rod Position System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indicated ranges are-picked for-verification of agreement with demanded position.
I l
l CATAWBA - UNITS 1&2 B 3/4 1-3b Amendment No. 82 (Unit 1)
Amendment No. 76 (Unit 2)
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