ML20236Q471
| ML20236Q471 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/13/1987 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236Q473 | List: |
| References | |
| NUDOCS 8711200080 | |
| Download: ML20236Q471 (11) | |
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'f UNITED STATES.
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NUCLEAR REGULATORY COMMISSION ~
g E-WASHINGTON, D. C. 20555 '
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- j DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION 1
SALUDA RIVER-ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING'L'ICENSE~
l Amendment No. 33,
j
~ License No NPF-35' 1.
The Nuclear Regulatory Comission (the Comission) 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) dated June 3, 1987, 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, as amended, 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 ccnducted 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 applicable requirements have 1
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-35 is hereby.
amended to read as follows:
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i (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Prcjects I/II
Attachment:
Technical Specification Changes Date of Issuance:
November 13, 1987 I
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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 LICENSE Amendment No. 24 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, 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. I and Piedmont Municipal Power Agency, (licensees) dated June 3, 1987, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the application, as amended, 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 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 amenoment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 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:
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_2-(2)- Technical Specifications -
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The Technical _ Specifications contained in Appendix A, as. revised l
through Amendment No. 24, are hereby incorporated into the' license.
1 The licensee shall operate..the facility in' accordance with the Technical Specifications and/ he Environ' mental Protection Plan.-
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'3.
This license amendment is effective as of its date of issuance; FOR THE NUCLEAR REGULATORY-COMMISSION, Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Projects I/II l
Attachment:
Technical Specification Changes
'l Date of Issuance: November 13, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT N0. 33-FACILITY OPERATING LICENSE NO. NPF-35.
DOCKET N0. 50-413 AND TO LICENSE AMENDMENT NO. 24 FACILITY' OPERATING LICENSE'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 areas of Lchange. The corresponding over-i leaf pages are also provided to maintain. document completeness.
Amended Overleaf Page Paae 3/4 1-14 3/4 1-13 3/4 1-15 3/4 1-16.
B 3/4 1-4 B3/4 1-3 l
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REACTIVITY CONTROL SYSTEMS j
SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
)
1)
Verifying the boron concentration in the water,.
2)
Verifying the contained borated water volume of the water source, and 4
3)
Verifying the Boric Acid Storage System solution 1 temperature when it is the< source of borated water.
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 the outside air temperature is either less than 70'F or greater than 100 F.
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CATAWBA - UNITS 1 & 2 3/4 1-13
I REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION i
3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within 112 steps (indicated position) of their group step counter demand position.
APPLICABILITY:
MODES 1* and 2*.
ACTION:
With one or more full-length rods inoperable due to being immovable a.
as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
L.
With more than one full-length rod misaligned from the group step l
counter demand position by more than 112 steps (indicated position),
be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With one full-length rod trippable but inoperable due to causes c.
other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than 112 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figure 3.1-la or Figure 3.1.lb, as applicable.
l The THERMAL POWER level shall be restricted pursuance to Specifi-cation 3.1.3.6 during subsequent operation, or 3.
The rod is declared inoperable and the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b)
The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
- See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
CATAWBA - UNITS 1 & 2 3/4 1-14 Amendment No. 33 (Unit 1)
Amendment No. 24 (Unit 2)
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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION
' ACTION (Continued) c)
A power distribution map is obtained from the movable N
incore detectors-and F (Z) and T are verified to be 0
AH within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and d)
The THERMAL' POWER 1evel is reduced to less than or
. equal to 75% of RATED THERMAL POWER within the next hour and within the following'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron _ Flux Trip Setpoint is_ reduced to less than or equal to 85%
of RATED THERMAL POWER.
d.
With more than one full-length rod trippable but inoperable due.to causes other than addressed by ACTION a above, POWER OPERATION may-continue provided that:
1.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the remainder of the rods in the bank (s) with' the inoperable rods are aligned to within 112 steps of the inoperable rods while maintaining the rod sequence and inser-tion limits of Figure' 3.1-la or Figure 3.1-lb, as applicable.
The THERMAL POWER level shall be restricted pursuant to-Specification 3.1.3.6 during subsequent operation, and 2.
The inoperable rods are restored to OPERABLE status within-72 hours.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except'during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.
'l CATAWBA - UNITS 1 & 2 3/4 1-15 Amendment No. 33 (Unit 1)
Amendment No.24 (Unit 2)
i TABLE 3.1-1 1
ACCIDENT ANALYSES REQUIRING REEVALUATION
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g IN THE EVENT OF AN IN0PERABLE FULL-LENGTH R0D Rod Cluster Control Assembly Insertion Characteristics l
Rod Cluster Control Assembly Misalignment i
Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in large
'l Pipes Which Actuates the Emergency Core Cooling. System
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Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System Pipe, Ruptures (Loss of Coolant Accident)
Major Secondary Coolant System Pipe Rupture i
Rupture of a Control Rod Drive Mechanism. Housing (Rod Cluster Control i
Assembly Ejection) 1 i
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CATAWBA - UNITS 1 & 2 3/4 1-16
REACTIVITY CONTRDL SYSTEMS BASES B0 RATION 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 E0L 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 reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection 5'ystem 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 285 F provides assurance I
that a mass addition pressure transient can be relieved by the operation of a single PORV.
1 The boron capability required below 200 F is sufficient to provide a l
SHUTDOWN MARGIN of 1% Ak/k after xenon decay and cooldown from 200 F to 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 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.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The spec'.fications of this section ensure that:
(1) acceptable power distribution limits are maintained, (2) the minimum SHUTOOWN 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 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, 120 and 228 steps withdrawn for the Control Banks and 18, 210 and 228 steps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of indication.
4 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.
CATAWBA - UNITS 1 & 2 B 3/4 1-3
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REACTIVITY CONTROL SYSTEMS BASES MOVABLE CONTROL ASSEMBLIES (Continued)
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 l
of peaking factors and a restriction in THERMAL POWER.
These restrictions pro-vide assurance of fuel rod integrity during continued operation.
In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results 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 T greater than or avg equal to 551 F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced 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 LCOs 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.
During performance of the Control Rod Movement periodic test (Specifica-tion 4.1.3.1.2), there have been some " Control Malfunctions" that prohibited I
l a control rod bank or group from moving when selected, as evidenced by the demand counters and DRPI.
In all cases, when the control malfunctions were corrected, the rods moved freely (no excessive friction or mechanical inter-ference) and were trippable.
This surveillance test is an indirect method of verifying the control rods are not immovable or untrippable.
It is highly unlikely that a complete control rod bank or bank group is immovable or untrippable.
Past surveillance and operating history provide evidence of "trippability".
Based on the above information, during performance of the rod movement test, if a complete control rod bank or group fails to move when selected at d can be attributed to a " Control Malfunction", the control rods can be considered
" Operable" and plant operation may continue while ACTIONS c. and d. are taken.
If one or more control rods fail to move during testing (not a complete bank or group and cannot be contributed to a " Control Malfunction"), the affected control rod (s) shall be declared " Inoperable" and ACTION a taken.
(
Reference:
W 1etter dated December 21, 1984, NS-NRC-84-2990, E. P. Rahe to Dr. C. O. Thomas)
CATAWBA - UNITS 1&2 B 3/4 1-4 Amendment No. 33 (Unit 1)
Amendment No. 24 (Unit 2)