ML20059D464
| ML20059D464 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/30/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059D466 | List: |
| References | |
| NUDOCS 9009070051 | |
| Download: ML20059D464 (10) | |
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UNITED STATES e
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NUCLEAR REGULATORY COMMISSION -
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. DUKE POWER COMPANY c
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NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION
[j SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 s
CATAWBA NUCLEAR STATION UNIT 1 L
q AMENDMENT T0 FACILITY OPERATING LICENSE i
i Amendment No. 78 1
License No. NPF '
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The Nuclear Regulatory Comission (the Cominion) has found that:
}i A.
The application for amendment.to the Catawba Nuclear Station, Unit l' I
(the' facility)FacilityOperatingLicenseNo.NPF-35filedby.the-DukeL Power Company acting for itself, North' Carolina Electric
' Membership)' Corporation and Saluda River Electric Cooperative, Inc.
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-(licensees dated December 21, 1987, as supplew.nted July 14,.1989, Ls a
nApril 19.and June 12, 1990, complies with-the standards and requirements of the Atomic Energy Act of.1954, as -amended tthe Act), and the:
4
'Comission's' rules and regulations as set 4rth in 10 CFR Chapter I;.
t B.
JThe; facility will operate in conformii.y with the application, the f
. provisions of the Act, and-the rules and regulations of the
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' Comission;
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l; There'is reasonable assurance (1) that the activities authorized by l
C.
Ei this amenoment can be conducted without endangering:the health and
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safety of the public,'and (ii) that such activities will be conducted in complience with the Comission's regulationsEset forth
-in 10 CFR Chapter I; w
D.
<The issuance of this amendment will not be inimical to the comon' n 7-
' defense and security or to the health and safety of the public; and
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E.:
The issuance of this amendment is in accordance with 10 CFR Part 51' of the-Comission's regulations and all applicable requirements have s
'been satisfied.
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the' attachment to this license amenonent, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is-hereby atended to read as follows::
Technical Specific 6tions The Technical Specifications contained in Appenoix A, as revised through Akcndment No. 78. and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incerporated into this license. Duke Power Company shall.
operate th's facility in accordance with the Technical Specifications y
and the Environmental-Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b.?k b hl. [ N David B. Matthews, Director' Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor. Regulation
Attachment:
LTechnical Specification Changes Date of Issuance:
August 30,-1990
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_ NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT' MUNICIPAL POWER AGENCY-DOCKET NO. 50-414 1
n CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT T0 FACILITY ODERATING LICENSE 1
Amendment No.
72 License No. NPF-52 1.
. The Nuclear Regulatory Comission (the Comission) has found that:
^
. A.
The application for amenoment to the Catawba Nuclear Station, Unit '2 -
(the f acility) Facility Operating License No. NPF-52 filed by the-Duke Power Company acting for itself, North Carolina Munici al Power Agency No. I and Piedmont Municipal Power Agency (licensees dated December 21, 1987, as' supplemented July 14,'1989, April 19, and June 12, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's i
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 o
Commission; j
-C.
There is reasonable assurance-(1)~ that the activities authorized by this amendment can be conducted without endangering the health and safety'of-thepublic,and-(ii)thatsuchactivitieswillbe 1
conducted in compliance with the Commission's' regulations-_ set-forth in 10 CFR Chapter I; D.
.The issuance of this 6mendment 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 emendment is in accordance with 10 CFR Part 51 of the-Conraission's regulations and all applicable requirements have been satisfico.
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Accordingly, th'e license is hereby anended by page changes to the Technical' Specifications as' indicated in the attachnent to this license amendment, i
and Paragraph 2.C.(2) of facility Operating License No. NPF-52 is' hereby -
anended to. read as ?ollows:
Technical Specifications The Technical Specifications contained in Appendix A..as revised.
through Amendnent No. 72, and the Environmental Protection Plan contained in Appendix B, both of which are attacheo hereto,~are hereby incorporated into this license. Duke Power Company shall 7
operate.the. facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendnent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f/2lh N' Yt;b h.
David B. Matthews, Director Project Directorate 11-3~
Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation L
Attachnent:
Technical Specification Changes Dateiof--Issuant.c: August 30, 1990 e
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ATTACHMENT'TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 ANp TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICEt;SE NO. NPF-52 DOCKET NO. 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 arc 6s of change.
Remove Pay insert Page 3/4 7-14 3/4 7-14 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7 16 B 3/4 7-3a B 3/4 7-3a B 3/4 7-4 B 3/4 7-4 j
PLANT SY. STEMS
~ 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM-LIMITING CONDITION FOR OPERATION 3.7.6 Two~ independent Control Room Area Ventilation Systems shall be 7
APPLICABILITY. ALL MODES 9
ACTION:
(Units 1 and 2)
MODES l', 2, 3 and 4:
With one Control Room Area Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days 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 />.
MODES 5 and 6:
With one Control Room Area Ventilation System inoperable, restore a.
the inoperable system to OPERABLE l status within 7 days or-initiate and maintain operation of the remaining OPERABLE Control Room Area j
Ventilation System.
l b.-
With both Control Room Area Ventilation Systems inoperable, or with the OPERABLE Control Room Area Ventilation _ System, required to be operating by ACTION a., not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
The provisions of Specification 3.0.4 are not appifcable.
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i SURVEILLANCE REQUIREMENTS
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4.7.6 Each Control Room Area' Ventilation System shall be demonstrated l
OPERABLE:
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i 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 verifying that the control room a.
air temperature is less than or equal to 90'F; b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating,
^q from the control room, flow through the HEPA filters and activated carbon adsorbers and. verifying that the system operates for at least 10 continuous, hours with the heaters operating; CATAWBA - UNITS 1 & 2 3/4 7-14 Amendment No. 7B (Unit 1)
Amendment No. 72 (Unit 2)
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- PLANT SYSTEMS:
SURVEILLANCE' REQUIREMENTS (Cobtinued)
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At least"once per-18 months or (1) after any structural maintenance on.the HEPA filter or activated carbon adsorber housings, or (2) following. painting, fire, or chemical release in any ventilation 1
zone communicating with the system by:
1)i Verifying that the cleanup system satisfies the in place
, penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in l
. Regulatory Position C.S.a. C.S.c, and C.S.d* of Regulatory.
Guide 1.52, Revisions 2, March 1978, and the system flow 1
rate is 6000 cfm i 10%;:
1 2)
Verifying, within 31 days af ter removal. that a laboratory i
analysis of_a1 representative activated carbon sample obtained in eccordance.with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl. iodide penetration of-less than 0.175%; and l
3)
Verifying a system flow rate of 6000 cfm +'10% during system operation when tested in accordance with XNSI N510-1980.
L d.
After every 1440-hours of activated carbon adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis **
of a representative activated carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52,' Revision 2, L
March 1978, meets the laboratory testing criteria of Regulatory Posi-L tion C 6.a of Regulatory Guide 1.52, Bevision 2, March 1978, for a l
methy1' iodide penetration of less'than 0.175%;
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At least once per 18 months by:
1)
Verifying that the pressure drop across the combined HEPA filters, activated carbon.adsorber banks, and moisture separstors is less than 8 inches Water Gauge while operating the system at a flow rate of 6000 cfm t,10%;
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'2)
Verifying that on a High Radition-Air Intake, or Smoke. Density-L High test signal, the system automatically isolates the fected I
intake from outside air with recirculating flow through the HEPA ll filters and activated carbon adsorber bank.s; 3)
Verifying that the system maintains the control room at a posi-tive pressure of greater than or equal to 1/8 inch Water Gauge o
relative-to adjacent areas at less than or equal to pressuriza-tion flow of 4000 cfm to the control room during system operation; 4)
Verifying that the heaters dissipate 25 1 2.5 kW, and
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- The-requirement for reducing refrigerant concentration to 0.01 ppm may be
-satisfied by operating the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with heaters on and operating.
,** Activated carbon adsorber samples are tested at 30 degree C.
l CATAWBA - UNITS 1 & 2 3/4 7-15 Amendment No. 78 (Unit 1)
L Amendment No. 72 (Unit 2)
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p'LANT ' SYSTEMS :-
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~ SURVEILLANCE' REQUIREMENTS (Continued)
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_ Verifying that on a High Chlorine / Toxic Gas test signal, the system automatically isolates the affected intake from outside air with recirculating flow through the HEPA filters and acti-vated carbon adsorbers banks within 10 seconds.(plus air. travel-time between the detectors and the isolation dampers).
J f.
Af ter each complete or partial replacement'of a HEPA filter bank, by-verifying that-the cleanup system satisfies the =in place penetration and bypass leakage _ testing acceptance criteria of less than 0.05%
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in accordance with ANSI N510-1980'for a DOP test aerosol while operating the system at a flow rate of 6000 cfm i 10%; and g.-
After each complete or partial replacement of an activated carbon adsorber' bank, by verifying that the cleanup system satisfies the-in place. penetration and-bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a
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halogenated hydrocarbon refrigerant test gas while operating the system:at a flow rate of 6000 cfm tildC.
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- CATAWBA. UNITS 1 & 2 3/4 7-16 Amendment No.78 (Unit 1)
Amendment No.72 (Unit 2)
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. PLANT-SYSTEMS BhSES i
3/4.7.5 STANDBY NUCLEAR SERVICE WATER POND The limitations on the standby nuclear service water pond (SNSWP) level and temperature ensure that sufficient cooling capacity is available to either:
-(1) provide normal cooldown of the facility, or (2) mitigate the effects of accident conditions within acceptable limits.
The limitations en minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and is consistent with the recommend-
_ations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"
March'1974.
The peak containment pressure analysis assumes that the Nuclear Service-Water (RN) flow to the Containment Spray and Component Cooling heat exchangers has a temperature of 86.5'F.
This. temperature is important in that it, in part, determines the capacity for energy removal from containment.
The peak containment pressure occurs when energy addition to containment (core decay-heat) is balanced by-energy removal from these heat exchangers.
This balance-is reached far.out in time, after the transition from injection to cold leg-recirculation and after ice melt.
Because of the effectiveness of the ice bed in condensing the' steam which passes through it, containment pressure is insensitive toismall variations in containment spray temperature prior to ice meltout.
To ensure that the RN temperature assumptions are met, Lake Wylie temperature ~is monitored. :During periods of time while Lake Wylie temperature 1
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'is greater than-86.5 F, the emergency procedure for transfer of ECCS flow-L paths to' cold leg recirculation directs the operator to align at least one
- train of containment spray to be cooled by a loop of Nuclear Service Water which is aligned to the SNSWP.
3/4 7.6 CONTROL ROOM AREt VENTILATION SYSTEM 1
m The OPERABILITY of the Control Room Area Ventilation System ensures that:
1 (1) the< ambient air temperature does not exceed the allowable temperature for
. continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all crulible accident conditions.
Operation of the system with the heaters operating to maintain low humidity using automatic control for l
at least 10 continuous hours in_a 31-day period is sufficient to reduce the L
buildup.of moisture on the adsorbers and HEPA filters.
The Control Room Area Ventilation System filter units have no bypass line.
Either Control Room Area Ventilation System train must operate in the filtered mode continuously.
When L
a train is in operation, its associated heater also runs continuously.
The l
-0PERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent.
This limitation is con-
.sistent with the requirements of General Design Criterion 19 of Appendix A, 10'CFR Part 50.
ANSI N510-1980 will be used as a procedural guide for surveil-lance testing.
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,, CATAWBA - UNITS 1 & 2 B 3/4 7-3a Amendment No. 78 (Unit 1)
L Amendment No. 72 (Unit 2)
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' PLANT SYSTEMS-
' BASES
.The 18-month surveillance to verify a positive pressure of greater than 1/8 inch watet gauge, with less-than or ewal'to 4000 cfm of pressurization flow, is to be conducted using only one intake from outside air open.
By testing the capability to> pressurize the control toom using each intake individually, the design basis which assumes reopening of the two intakes following isolation'on chlorine, smoke or radiation, is tested.
3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM The OPERABILITY of the Auxiliary Building Filtered Exhaust System ensures that radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment.
Operation of.the system with the heaters operating to maintain. low humidity using automatic control for at least 10 continuous hours in a 31-day-period is sufficient to reduce.the buiM up of moisture on the adsorbers and HEPA filters.
The operation of this system and the resultant effect on offsite dosage calcu-1ations was not taken credit for in the safety analyses.
However, the operation
-of this system and the resultant effect on the NRC staff's offsite dose calcula-tions was assumed in the staff's SER, NUREG-0954.
ANSI N510-1980 will be used "as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main-I tained during and following a seismic or other event. initiating dynamic loads.
L l
Snubbers are classified and grouped by design and manufacturer but not_by L
size.
For example,1 mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B"'
-for the purposes of this Technical Specification would be of a-different type, as would hydraulic snubbers from either manufacturer.
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, A list of individual-snubbers with detailed information of snubber location and size and of system affected shall be available-at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall p
be. determined and approved by the Catawba Safety Review Group.
The determination shall be based upon the existing radiation levels and the expected time to per-E form a' visual inspection in each snubber location as well as other factors asso-ciated-with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.) and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletions of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
CATAW8A - UNITS 1 & 2 B 3/4 7-4 Amendment No. 78 (Unit 1)
Amendment No. 72 (Unit 2)
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