ML20237D518
| ML20237D518 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/11/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237D520 | List: |
| References | |
| NUDOCS 8712240004 | |
| Download: ML20237D518 (8) | |
Text
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UNITED STATES
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1 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 3
CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 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 October 14, 1987, and supplemented November 18, 1987, 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, 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 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 Comission'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-35 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.
36, and the Environmental Protection Plan 8712240004 871211 PDR ADOCK 05000413 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.
1 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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1 Kahtan N. Jabbour, Acting Director 1
Project Directorate II-3
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Division of Reactor Projects I/II 1
Attachment:
i Technical Specification Changes Date of Issuance: December 11, 1987 I
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NUCLEAR REGULATORY COMMISSION 7
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DUKE POWER COMPANY
' NORTH CAROLINA MUNICIPAL POWER AGENCY NO. l' PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE ~
Amendment No. 28 License No. NPF-52 1.
The Nuclear Regulatory Comission (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.1 and Piedmont Municipal Power Agency, (licensees) dated 0ctober 14, 1987, and supplemented November 18, 1987, 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, as amended, the provisions of the Act, and the rules and regulations of l
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 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 Comission'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 4
to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, and the Environmental Protection Plan
.s.
. 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
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Kahtan N. Jabbour, Acting Director Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance: December 11, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 36.
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FACILITYfERATINGLICENSENO.NPF-35 i
DOCKET NO. 50-413 AND j
TO LICENSE AMENDMENT NO. 28 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 page is identified by Amendment number and contains vertical lines indicating the areas l f change. The corresponding o
overleaf page is also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 6-16 3/4 6-15 B3/4 6-3 B3/4 6-4
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of carbon adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis.~of a repre-l sentative carbon sample obtained in accordance 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 1%;
d.
At least once per 18 months by:
1)
Verifying that the pressure drop across the combined HEPA filters, 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 Phase "A" Isolation test signal,"*
3)
Verifying that the filter cooling electric motor-operated bypass valves can M 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 g
5)
Verifying that the pre-heaters dissipate 45 i 6.7 kW.
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After each complete or partial replacement of a HEPA filter bank, by e.
verifying that the cleanup system satisfies the in place penetra-l i
. tion and bypass leakage testing acceptance criteria of less than 1%
(Unit 1), 0.05% (Unit 2) in accordance with ANSI H510-1980 for a DOP test aerosol while operating the system at a flow rate of 9000 cfm 10%; and f.
After each complete or partial replacement of a carbon adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI H510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 9000 cfm i 10%.
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- This surveillance need not be performed until prior to entering HOT SHUTDOWN l '-
following the Unit 1 first refueling.
lf CATAWBA - UNITS 1 & 2 3/4 6-15 l
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CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.1.9 Each containment purge supply and exhaust isolation valve shall be OPERABLE and:
a.
Each containment purge supply and/or exhaust isolation valve for the lower compartment and the upper compartment (24-inch), 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 ret,pirable 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.
ACTION:
a.
With any containment purge supply and/or exhaust isolation valve for the lower compartment and the upper compartment, or instrument room, or Hydregen Purge System open or not sealed closed, close 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 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 />.
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 />.
c.
With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifi-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 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 />.
SURVEILLANCE REQUIREMENTS 4.6.1.9.1 Each containment purge supply and/or exhaust isolation valves for the lower compartment and the upper containment, or instrument room, or Hydrogen Purge System shall be verified to be sealed closed at least once per 31 days.
4.6.1.9.2 The cumulative time that the Containment Air Release and Addition System has been open during a calendar year shall be determined at least once per 7 days.
CATAWBA - UNITS 1 & 2 3/4 6-16 Amendment No. 36 (Unit 1)
Amendment No. 28 (Unit 2)
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C0NTAINMENT S STEMS BASES l
3_/_4.6.1.8 ANNULUS VENTILATION SYSTEM The OPERABILITY of the Annulus Ventilation System ensures that during LOCA j
conditions, containment vessel leakage into the annulus will be filtered through the HEPA filters and carbon adsorber trains prior to discharge to the i
atmosphere.
Operation of the system with the heaters operating to maintain low j
humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
This requirement is necessary to meet the assumptions used in the safety analyses and limit the SITE B0UNDARY radiation doses to within the dose guide-
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line values of 10 CFR Part 100 during LOCA conditions. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
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3/4.6.1.9 CONTAINMENT PURGE SYSTEMS l
The containment purge supply and exhaust isolation valves for the lower compartment and the upper compartment (24-inch), and instrument room (12-inch),
and the Hydrogen Purge System (4-inch) are required to be sealed closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA.
Maintaining these valves sealed closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the Containment Purge System.
To provide assurance that these containment valves cannot be inadvertently opened, the valves are sealed closed in accord-ance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.
The use of the containment purge lines is restricted to the 4-inch Con-l tainment Air _ Release and Addition System valves since, unlike the lower compart-i ment and the upper compartment, instrument room, and the Hydrogen Purge System valves, these 4-inch valves are capable of closing during a LOCA.
Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not be exceeded in the event of an accident during containment purging operation.
Operation with the line open will be limited to 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> during a calendar year for the l
4-inch valves.
The total time the containment purge (vent) system isolation j
valves may be open during MODES 1, 2, 3, and 4 in a calendar year is a function j
of anticipated need and operating experience.
Only safety-related reasons; e.g., containment pressure control or the reduction of airborne radioactivity to facilitate personnel access for surveillance and maintenance activities, may I.
be used to justify the opening of these isolation valves.
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Leakage integrity tests with a maximum allowable leakage rate for contain-ment purge supply and exhaust valves will provide early indication of resilient material seal degradation and will allow opportunity for repair before gross leakage failures could develop.
The 0.60 L leakage limit of Specification a
3.6.1.2b. shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
l CATAWBA - UNITS 1 & 2 B 3/4 6-3 Amendment No. 36 (Unit 1)
Amendment No. 28 (Unit 2)
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l CONTAINMENT'SYSTCMS l
BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS I
The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are f
consistent with the assumptions used in the safety analyses.
However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere, and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with those assigned other inoperable ESF equipment.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within f
the time limits specified for those isolation valves designed to close auto-matically ensures that the release of radioactive material to the environ-ment will be consistent with the assumptions used in the analyses for a LOCA.
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with:
(1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment.
These Hydrogen Control Systems are consistent with
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the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations Following a LOCA," March 1971.
The OPERABILITY of at least 35 to 36 igniters per train (70 of 72 for both trains) ensures that the Distributed Ignition System will maintain an effective coverage throughout the containment provided the two inoperable ignitors are not on corresponding redundant circuits which provide coverage for the same region.
This system of igniters will initiate combustion of any significant amount of hydrogen released after a degraded core accident.
This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.
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CATAWBA - UNITS 1 & 2 B 3/4 6-4
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