ML20116D626
| ML20116D626 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/30/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20116D628 | List: |
| References | |
| NUDOCS 9608020249 | |
| Download: ML20116D626 (8) | |
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UNITED STATES s
g-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. NPF-35 1.
The Nuclear Regulatory Commission (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. (licar w), dated January 26, 1996, as supplemented by letters f.ted May 6, May 20, and June 5, 1996, 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 i
Commission; C.
There is reasonable assurance (i) 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 common 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 Commission's regulations and all applicable requirements have been satisfied.
9608020249 960730 PDR ADOCK 05000413 P
l 2.
Accordingly, the license is hereby amended 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.
i NPF-35 is hereby amended to read as follows:
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 150, which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
l FOR THE NUCLEA REGULATORY COMMISSION 4
/
rbert N.
erkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technica1' Specification Changes Date of Issuance:
July 30, 1996 4
i s
]
m-
l l
ATTACHMENT TO LICENSE AMENDMENT NO. inn l
FACILITY OPEFATING LICENSE NO. NPF-35 DOCKET NO. 50-413 i
l Replace the following pages of Appendix "A", Technical Specifications, with the enclosed pages.
The revised pages are identified by amendment number and l
contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-14 3/4 6-14 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 1
3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4.**
l ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY 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 />.
SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by 0PERABLE containment automatic isolation i
valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3; j
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and After each closing of each penetration subject to Type B testing, c.
except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at a pressure not less than P,,14.68 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pur-suant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than 0.60 L,.
l
- Except valves, blind flanges, and deactivated automatic vaives which are located inside the annulus or the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
- A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to seven (7) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4.
Each valve will be sealed closed prior to initial entry into Mode 2.
CATAWBA - UNIT 1 3/4 6-1 Amendment No. 150
CONTAINMENT SYSTftLS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or eoual to L, 0.30%
a.
by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,14.68 psfg.
b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,,
and A combined bypass leakage rate of less than 0.07 L,tainment bypass c.
for all pene-trations identified in Table 3.6-1 as secondary con leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
- l ACTION:
With:
(a) the measured overall integrated containment leakage rate exceeding 0.75 L,, or (b) the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L,, or (c) toe combined bypass leakage rate exceeding 0.07 L bined leakage rate for all penetrations
, restore the overall integrated leakage rate to less than 0.75 L, and the com and valves subject to-Type B and C tests to less than 0.60 L combined bypass leakage rate to less than 0.07 L, prior to in, and the creasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 Type A containment leakage rates shall be demonstrated as required by 10 CFR 50.54(o) and Appendix J of 10 CFR Part 50, Option B, as modified by approved exemptions, and in accordance with the guidelines of Regulatory Guide 1.163, September, 1995.
- A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower comnartment open in Modes 3 and 4 following the steam generator replacement outage. The cumulative time for having the valves open in Modes 3 and 4 is limited to seven (7) days. All other provisions of this specification apply with the exception of those containment purge valves open in Modes 3 and 4.
Each valve will be sealed closed prior to initial entry into Mode 2.
CATAWBA - UNIT 1 3/4 6-2 Amendment No.150
~
CDNTAINMENT SYSTEMS
}
ANNULUS VENTILATION SYSTEM l'
LIMITING CONDITION FOR OPERATION 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.**
I ACTION:
a.
With one Annulus Ventilation System inoperable for reasons other i
than the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5, restore the. inoperable system to OPERABLE status within 7 days or be in at i
least H0T 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 />.
b.
With the pre-heaters tested in 4.6.1.8.a and 4.6.1.8.d.5 inoperable, restore the inoperable pre-heater.s to operable status within 7 days, or file'a Special Report in accordance with Specification 6.9.2 within 30 days specifying the reason for inoperability and the planned actions to return the pre-heaters to operable status.
SURVEILLANCE REQUIREMENTS 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, 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 pre-heaters operating; b.
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 zone communicating with the system by:
1)
Verifying that the cleanup system satisfies the in-place pene-tration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a, C.5.c, and C.S.d* of Regulatory Guide 1.52 Revision 2, March 1978, and the system flow rate is 9000 cfm 110%;
- 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.
- A one-time change is granted in Modes 3 and 4 to allow repair activities for the containment purge supply and/or exhaust isolation valves for the upper and lower compartment that were open in Modes 3 and 4 following the steam generator replacement outage.
CATAWBA - UNIT 1 3/4 6-14 Amendment No. 150
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)
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, March 1978, and tested per ASTM D3803-89 has a methyl iodide penetration of less than 4%;
and 3)
Verifying a system flow rate of 9000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 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, March 1978, and tested per ASTM-D3803-89 has a methyl iodide penetration of less than 4%;
d.
At least once per 18 months by:
1)
Verifying that the pressure drop across the combined HEPA fil-ters, activated carbon adsorber banks, and moisture separators is less than 8 inches Water Gauge while operating the system at a flow rate of 9000 cfm i 10%-
2)
Verifying that the system starts automatically on any safety injection test signal, 3)
Verifying that the filter cooling electric motor-operated bypass valves can be manually opened, 4)
Verifying that each system produces a negative pressure of greater than or equal to 0.5 inch Water Gauge in the annulus within 1 minute after a start signal, and 5)
Verifying that the pre-heaters dissipate 45 i 6.7 kW at a nominal voltage of 600 vac, e.
After 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 1% in accordance with ANSI N510-1980 for a D0P test aerosol while operating the system at a flow rate of 9000 cfm i 10%; and f.
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 1% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a i
flow rate of 9000 cfm i 10%.
i
- Activated carbon adsorber samples are tested at 30 degrees C and 95% RH.
CATAWBA - UNIT 1 3/4 6-15 Amendment No.150 l
CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.1.9 Each cont.ainment purge supply and exhaust isolation valve shall be OPERABLE and:
a.
Each containment purge supply and/or exhaust isolation valve for i
l the lower compartment and the upptr compartment (24-inch),
l instrument room (12-inch), and the Hydrogen Purge System (4-inch) shall be sealed closed, and b.
The Containment Air Release and Addition System (4-inch) isolation valve (s) may be open for up to 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> during a calendar year for pressure control, for ALARA and respirable air quality considerations for personnel entry and for surveillance tests that require the valve (s) to be open.
APPLICABILITY: MODES 1, 2, 3, and 4.*
l ACTION:
a.
With any containment purge supply and/or exhaust isolation valve for the lower compartment and the upper compartment, or instrument l
room, or Hydrogen Purge System open or not sealed closed, close l
and/or seal closed that valve or isolate the penetrations (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise be in at least H0T 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 />.
b.
With the Containment Air Release and Addition System isolation valve (s) open for more than 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> during a calendar year or for reasons other than given in 3.6.1.9b. above, close the open valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 />.
l c.
With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifi-l cations 4.6.1.9.3 and/or 4.6.1.9.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise be in at least HOT l
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 l
4
- A one-time change is granted to have the containment purge supply and/or exhaust isolation valves for the upper and lower compartment open in Modes 3 and 4 following the steam generator replacement outage.
The cumulative time for having the valves open in Modes 3 and 4 is limited to seven (7) days. All other provisions of this specification apply with the exception 3
of those containment purge valves open in Modes 3 and 4.
Each valve will be sealed closed prior to initial entry into Mode 2.
CATAWBA - UNIT 1 3/4 6-16 Amendment No. 150