ML20236Q676
| ML20236Q676 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/10/1987 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236Q678 | List: |
| References | |
| NUDOCS 8711200224 | |
| Download: ML20236Q676 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION yg WASHINGTON, D. C. 20555 g
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
l DOCKET N0. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-35 1
1 1.
The Nuclear Regulatcry Commission (the Corimission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. t;PF-35 filed by the Duke Power Company actirig for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) j dated July 31, 1987, complies with the standard 3 and requirements of l
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; i
B.
The facility will operate in conformity with the application, as j
'f.
amended, the provisions of the Act, and the rules and regulations cf i
the Commissior; C.
There is reasonable assurance: (1) that the activities authorized by j
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 ta 20 CFR Chapter I; j
D.
The issuance of this license amendment will not be inimical to the corrmon defense and security or to the health and safety of the public; E.
The issuance of this arrendment is in accordance with 10 CFR Part 51 1
of the Commission's regulations arid all applicable requirements heve been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the 6ttachments to this license amendrnent and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amer"'ed to read as follows:
(2) Technical Specifications and Environmental Protection Plcn The Technical Specifications contained in Appendix A, as revised through Amendment No.
31, and the Environmental Protection Plan 8711200224 871110 PDR ADOCK 05000!!:3 P
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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 Lawrence P. Crocker.,, Icting Director l
Project Directorai.o II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance: November 10, 1987 j
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',g NUCLEAR REGULATORY COMMISSION WASMNGTON, D. C. 205L5 DUKE POWER COMPANY l
NORTH CAROLINA MUNICIPAL F0HER AGENCY N0. 1 i
PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT P
/NENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Commission) has found tnat:
A.
The application for amendment to the Catawba Nuclear Statinn, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Prwer Agency., (licensees) dated July 31, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comnrission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as J
amended, the provisions of the Act, and the rules and regulations of L,
the Comission; 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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; 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.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating license No. NPF-52 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
22, and the Environmental Protection Plan
l l 3 contained in Appendix B, both of which are' attached hereto, are hereby incorporated into this. license.. Duke Power Company shall
'f operate the facility in accordance with the Technical Specifications-l and the Environmental Protection Plan.
j 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION
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l Lawrence P. Crocker, Acting Director.
Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes 1
Date of Issuance: November 10, 1987 j
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1 ATTACHMENT TO~ LICENSE AMENDMENT NO.__31' i
FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 i
AND 1
TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET N0. 50-414 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 also provided:to maintain document completeness.
'knended Overleaf-Page Page 3/4 5-1 3/4 6-2 3/4 5-la (new page)
B 3/4 5-1 B 3/4 5-2 l
l l.
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS COLD LEG INJECTION LIMITING CONDITION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:
a.
The discharge isolation valve open, b.
A contained borated water volume of between 7853 and 8171 gallons, c.
A boron concentration of between-1900 and 2100 ppm, d.
A nitrogen cover pressure of between 385 and 481 psig, and A water level and presdure channel OPERABLE.
e.
APPLICABILITY:
MODES 1, 2, and 3*.
ACTION:
a.
With one cold leg injection accumulator inoperable, except as a result of a closed isolation valve or boron concentration less than 1900 ppm, l
restore the inoperable accumulator 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
I b.
With one cold leg injection accumulator inoperable due to the isolation valve being closed, either immediately open the isolation
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valve or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN L,
within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one accumulator inoperable due to boron concentration.less than 1
1900 ppm and:
1)
The volume weighted average bor.on concentration of the three limiting accumulators 1900 ppm or greater, restore the inoperable accumulator to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the low boron determination 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 reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2)
The volume weighted average boron concentration of the three limiting accumulators less than 1900 ppm but greater than 1500 ppm, restore the inoperable accumulator to OPERABLE status or return the volume weighted average boron concentration of-the three limiting accumulators to greater than 1900 ppm and-enter ACTION c.1 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the low baron determination or be in 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 reduce pres-surizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- Pressurizer pressure above 1000 psig.
CATAWBA - UNITS 1 & 2 3/4 5-1 Amendment No.'31 (Unit 1)'
Amendment No. 22 (Unit 2)
l EMERGENCY CORE COOLING SYSTEMS
. LIMITING CONDITION FOR OPERATION (Continued)
)
1 3)
The' volume weighted average boron concentration of the three limiting accumulators 1500 ppm or less, return the volume i
weighted average boron concentration of the three limiting:
1 1
accumulators'to greater than 1500 ppm and enter ACTION c.2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the. low boron determination or.be in 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 reduce pressurizer pres-i sure to less than 1000 psig within.the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
j SURVEILLANCE REQUIREMENTS l
4.5.1.1.1 Each cold. leg injection accumulator shall be. demonstrated ~
OPERABLE:
1 a.
At-least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
)
1)
Verifying, by the absence of alarms,'the contained borated water volume and nitrogen cover pressure in the tanks,'and I
2)
Verifying that each cold: leg. injection accumulator isolation-i valve is open.
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' CATAWBA - UNITS 1 & 2 3/4 5-la Amendment No.' 31' (Init - 1.'
Amendment No. 22 ([ nit'2'.
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EMERGENCY CORE COOLING SYSTEMS I
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SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 75 gallons by verifying H
the boron concentration of the accumulator solution; 4
c.
At least once per 31 days when the Reactor Coolant System pressure _
is above 2000 psig by verifying that power is removed from the isolation valve operators on Valves NI54A, NI65B, NI76A, and NI88B and that the respective circuit breakers are padlocked; and d.
At.least once per 18 months by verifying that each cold leg injection accumulator isolation valve opens automatically under each of the following conditions:**
i 1)
When an actual or a simulated Reactor Coolant System pressure signal exceeds the P-11 (Pressurizer' Pressure Block of Safety Injedtion) Setpoint, and 2)
Upon receipt of a Safety Injection test signal.
4.5.1.1.2 Each cold leg injection accumulator water level and pressure channel shall be demonstrated OPERABLE:
i a.
At least once per 31 days by the performance of an ANALOG CHANNEL OPERATIONAL TEST, and b.
At least once per 18 months by the performance of a CHANNEL CALIBRATION.
o* This surveillance need not be performed until prior to entering HOT STANDBY following the Unit I refueling.
CATAWBA - UNITS 1 & 2 3/4 5-2 t,
R 3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATORS The OPERABILIT( of each Reactor Coolant System accumulator ensures that a sufficient 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 Reactor Coolant System pressure falls below the pressure of the accumulators.
This initial surge of water into the core provides i
the initial cooling mechanism during large pipe ruptures.
j The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.
The allowed down time for the accumulators are variable based upon boron concentration to ensure that the reactor is shutdown following a LOCA and that any problems are corrected in a timely manner. -Subcriticality is assured when boron concentration is above 1500 ppm, so additional down time is allowed when concentration is above 1500 ppm.
A concentration of less than 1900 ppm in any single accumulator or as a volume weighted average may be indicative of a pro-blem, such as valve leaksge, but since reactor shutdown is assured, additional time is allowed to restore boron concentration in the accumulators.
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 required.
[E 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 j
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 from the double ended break of the largest 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 coolant 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.
CATAWBA - UNITS 1 & 2 B 3/4 5-1 Amendment No. 31 (Unit 1)
Ataendment No. 22 (Unit 2)
EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
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 centrifugal charging pump to be inoperable below 285 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 OPERABILITY is maintained.
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 each 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 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank as part of the ECCS ensures that a sufficient supply of borated water is available for injection y
by the ECCS in the event of a LOCA.
The limits on minimum volume and boron
[
concentration ensura 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 cold condition following mixing of the refueling water storage tank and the Reactor Coolant System water volumes with all control 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 or other physical characteristics.
The limits on contained water volume and boron concentration of the refueling water storage tank also ensure a pH value of between 8.5 and 10.5 for the solution reticulated within containment after a LOCA.
This pH band mini-mizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
CATAWBA - UNITS 1 & 2 B 3/4 5-2
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