ML20012C914
| ML20012C914 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/21/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012C915 | List: |
| References | |
| NUDOCS 9003260108 | |
| Download: ML20012C914 (9) | |
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UNITED STATES
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. NUCLEAR REGULATORY COMMISSION 5
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x DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
l DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 Limnse No. NPF-35 L
1.
The Nuclear Regulatory Comission (the Commission) has found that:
I
'A.
The application for amendment to the Catawba Nuclear Station, Un't 1 i
(the-facility) Facility Operating Li nse No. NPF-35 filed by the Duke Power Conpany acting for itself, North Carolina Electric Menbership Corporation and Saluda River Electric Cooperative, Inc.,
-(licensees) dated November 10, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (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; 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 corpliance with the Commission'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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requimments have been satisfied.
b' 9003260108 900321 PDR ADOCK0500g3 y
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2 2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachment to this license anen&ent, 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 Amendnent No. 71
, are hereby incorporated into the license.
The licensee shall operate the facility in eccordance with the Technical Specific 4tions and the Envimnnental Protection Plan.
3.
This li:cose ament. tnt is cffective a.: of its date of issuance.
FOR 1hl fil) CLEAR REGULATORY COMIS$10N
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David B. Matthewr, Directot-Droject Directorate II-3
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1 Oivision of Reactor Projects-I/II Office of Nuclear Peactor Regulation Attachnent:
l Technical Specification Changes j
Date of Issuance: March 21, 1990 l
's 2
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amentent, and Paragraph 2.C.(2) of facility Operating Limnse No. NPF-35 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71
, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Envimnmental Protection Plan.
3.
This licent,e amendnent. is effective as of its date of issuance.
FOR M fiOCliAk REGULATORY C0t.M75SION
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David B. Matthews, Director l~
Project Directorate II-3 Division of Reactor Projects-1/II Office of Nuclear Reactor iegulation r
Attachment:
Technical Specification Changes l
Date of issuance: March 21, 1990 t
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDM0 hit MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATl_06 UNIT 2 1
AMFNDHENT TO TACILITY OPERAi!WG LICENSE Amewn.eut %. 65 Iciuinse No. NPF-52 L
Tim Nuc* car Resulttory Comitslo.i (the Cowission) ha! found that:
A.
The application for amerdnent to the Cataeba Nuclear Station. Dr.it 2 (the fa.cility) f acility Operating License No. NPT-52 filed by the Duk Power Company acting for itself, North Carolina Municipal Power Ageng No. I and Piedmont Nnicipal Power Ageny, (licensees) dated Noveit>er 10, 1989, complies with the standards and requirenents of the Atomic Energy Act of 1954, as anended (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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this arendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in corpliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendnent 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 atendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
.____.._._____.__._m___
l 2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachnent to this license anendnent, and Paragraph 2.C.(2) of facility Operating License No. NPF-52 is hereby anended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Aneadnent No. 65
, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license snenament is effective as of its date of issuana.
FOR 1HE NUCLEAR REGULATORY C0411SSION Lub David B. katthews, Director Project Directorate 11-3 Division of Reactor Projects-!/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: March 21, 1990
7 DATED:
March 21, 1990 AMENDMENT NO. 71 TO FACILITY OPERATING LICENSE NPF Catawba Nuclear Station, Unit 1 AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NPF Catawba Nuclear Station, Unit 2 DISTRIBUTION:
Docket File NRC PDR Local PDR PDi!I-3 R/F Cetawba R/F S. Vaiva 14-E-4 G. Lainas 14-H-3 D. Matthews 14-H-25 R. Tugram It-H-25 K. Jatneur 3 4-H-26 CGC-WF 15-0-18 b
F. Jordan NNPB-3302 P 150A W. Jones F1 197 ACTS ()0) {B)
- o. Gill P-135 fiPA/PA 17-F-2 ARH/LTHB AR-2015 J. Calvo 11-F-23 D. Hagan NNBB-3302
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. NPF-S2 DOCKET NO. 50-414 Rep' face the following pages of the Appecdix "A" Techr,1 cal Specifiest
.J The corresponding ever-the enclosed pages.
coctain vertical lines indicatine the areas of change.
1eci page is also provided to maintain document completeness.
Anended Page Overicaf Pag 3/4 1-20 3/4 1-19 3/4 1-22
.l B 3/41-3
5 REACTIVITY CONTROL SYSTEMS ROD DROP TIME LIMITING CONDITION FOR OPERATION The individual full-length shutdown and control rod drop time from 3.1.3.4 the fully withdrawn position shall be less than or equal to 3.3 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
T,yg greater than or equal to 551'F, and a.
b.
All reacter coolant pumps operating.
APPLICABIQ1Y: MODES 1 anti 2.
ACTION:
With the drop time of any full-length rod datermined to exceed the above limit, restore the rod drop time to within the above limit a.
prict to proceeding to MODE 1 cr 2.
With the rod drop times within ?imits but determined with three reactor conhnt pumps operating, operation inay proceed provided THERMAL POWER b.
is restricted to 12ss than or cqual to 66% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS The rod drop time of full-length rods shall be demonstrated through 4.1.3.4 measurement prior to reactor criticality:
For all rods following each removal of the reactor vessel head, a.
For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect b.
the drop time of those specific rods, and At least once per 18 months.
c.
CATAWBA - UNITS 1 & 2 3/4 1-19
REACTIVITY CONTROL SYSTEMS ROD OROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length shutdown and control rod drop time from the fully withdrawn position shall be less than or equal to 3.3 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
T,yg greater than or equal to 551*F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES 1 and 2.
ACTION:
a.
With the drop time of any full-length red determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
Citii the rod drop times witnir, limits but determired with tnree reactor coolant pumos operating, operation may proceed provided TF.ERMAL POWER is restricted to less than or equal to 56% of RATED T.HERMAL POWER.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:
a.
For all rods following each removal of the reactor vessel head, b.
For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and c.
At least once per 18 months.
CATAWBA - UNITS 1 & 2 3/4 1-19
o REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT LIMITINGC0f(DITIONFOROPERATION 3.1.3.5 All shutdown rods shall be withdrawn to at least 225 steps.
l APPLICABILITY:
MODES 1* and 2*#.
ACTION:
With a maximum of one shutdown rod less than 225 steps withdrawn, except for.
l survaillan:9 testing pctsuant to Specifiestic.n 4.1,3.1.2, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:
a.
Withdraw the rod to at least 225 steps, or l
b.
Declare the rod to be inoperabic and apply Specificatica 3.1.3.1.
l SURVEILLANCE REOUIREMEKTS n.
4.1.3.5 Each shutdown rod shall be detarmined to be withdrawn to at least 225 steps:
a.
Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an approach to reactor criticality, and b.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
l l
7 l
- See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
- With K,ff greater than or equal to 1.
l i
s CATAWBA - UNITS 1&2 3/4 1-20 Amendment No. 71 (Unit 1)
Amendment No. 65 (Unit 2)
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( Fully Withdrawn i 226 i
220
( 28%,226 )
(78%,226 I 200 BANKB 1M t0%,1621
- 3m,3g3',
160 I
140 f
g, 3pc BANK C bc 200 w{
80 e
8 SANKD E
go
( 0%,47 )
40 20
( 30%,0 i l
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0 20 40 ao 80 100
( Fully inserted )
RE LATIVE POWE R ( Percent )
FIGURE 3,1-1 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION Amendment No. 71 (Unit 1)
CATAW8A-UNITS 1 ed 2 3/4 1 - 22 Amendment No. 65 (Unit 2)
e.
REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)
MARGIN from expected operating conditions of 1.3% Ak/k after xenon decay and cooldown to 200'F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 16,321 gallons of 7000 ppm borated water from the boric acid storage tanks or 75,000 gallons of 2000 ppm borated water from the refueling water storage tank.
With the coolant temperature below 200'F one Boron Injection System is acceptable without single failure consideration on the basis of the stable teactivity condition of the reactor End the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Inje: tion Syste:n becomes inoperable.
The limitation for a maximum of one centrifugal charging pump to be OPERABLE tnd tne Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperabie below 28S'F provides assurance that a mass addi-tion pressure trar.sient can be relieved by the operation of a single PORV.
The boron r.:rpat,ility required below 200'F is sufficient to provide a SHUTDOWN MAP. GIN of 1% Ak/k r<fter xenon decay and cooldown from 200*F to This condition requires either 906 gallens of 7000 ppm borated water 140'F.
from the boric acid storage tanks or 3170 gallons of 2000 ppm boreted water from the refueling water storage tank.
The contained water volume limits include allowance for water not available because of discharge line location and 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.S 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 OPERABILITY of the control rod position indicators is analyses are limited.
required 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
- 12 steps.
at 24, 4B, 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 Since the Digital Rod Position System does not
- the full range of indication.
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.
CATAWBA - UNITS 1&2 B 3/4 1-3 Amendment No.71 (Unit 1)
Amendment No.65 (Unit 2) im g
i i
REACTIVITY CONTROL SYSTEMS 1
BASES BORATION SYSTEMS (Continued)
MARGIN from expected operating conditions of 1.3% Ak/k af ter xenon decay and cooldown to 200'F. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 16,321 gallons of 7000 ppm borated water from the boric acid stcrape tanks j
or 75,000 gallons of 2000 ppm borated water from the refueling water storage i
tank.
With the coolant 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 'naximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verif
)
OPERABLE pump to be inoperable below ?S5'y all charging pumps except the required F provides assurance that a mass addi-tion pressure transient can be relieved by the operation of a single PORV.
The boron capability required below 200'F is sufficient to provide a
]
SHUTDOWN MARGIN of 'M Ak/k after xenon decay and cooldown front 200*F to i
140'F.
This condition requires either 906 gallons of 7000 ppm borated water from the boric acid storage tanks or 3170 gallons of 2000 ppm borated water J
from the refueling water storage tank.
The contained water volume limits include allowance for water not available because of discharge line location and 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 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.
o 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 J
analyses 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.
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 operhting correctly over
'the full range of indication.
Since the Digital Rod Position System does not indicate the actual shutdown rod positico between 18 steps and 210 steps, only points in the indicated ranges are picked for verification of agreement with demanded position.
CATAWBA - UNITS 1&2 B 3/4 1-3 Amendment No.71 (Unit 1)
Amendment No.65 (Unit 2)
-