ML20078S790
| ML20078S790 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/22/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078S792 | List: |
| References | |
| NUDOCS 9502270196 | |
| Download: ML20078S790 (5) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. sanas anni o,s,...../
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendatat No. 105 License No. NPF-49 1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated May 18, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 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-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; 1
and i
E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements have been satisfied.
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9502270196 950222 PDR ADOCK 05000423 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in 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 the date of its issuance, to be implemented within 30 days of issuance.
i F0 THE NUCLEAR REGULATORY COMISSION l
b LO. tw Phillip F. McKee, Director
/
i Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications j
Date of Issuance:
February 22, 1995 t
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L ATTACHMENT TO LICENSE AMENDMENT NO.105 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Techitical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 9-13 3/4 9-13 B3/4 9-3 B 3/4 9-3 1
m REFUELINS OPERATIONS 3/4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEN LIMITING COM ITION FOR OPERATION 3.9.12 Two independent Fuel Building Exhaust Filter Systems shall be OPERABLE. At least one Fuel Building Exhaust Filter System shall be in operation whenever any evolution involving movement of fuel.within the storage pool or crane operations with loads over the storage pool is i'n progress.
APPLICABILITY: Whenever irradiated fuel with less than 60 days decay is in l
the storage pool.
ACIl0N:
a.
With one Fuel Building Exhaust Filter System inoperable, fuel movement within the storage pool or crane operation with loads over the storage pool may proceed provided the OPERABLE Fuel Building Exhaust Filter System is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.
b.
With no Fuel Building Exhaust Filter System 0PERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one Fuel Building Exhaust Filter System is restored to OPERABLE status.
c.
The provisions of Specifications 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12 The above required Fuel Building Exhaust Filter Systems shall be demonstrated OPERABLE:
a.
Within 31 days prior to moving fuel within or loads over the storage pool when irradiated fuel with less than 60 days decay is present by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers, and verifying a system flow rate of 20,700 cfm 110% and that the system operates for at least 10 continuous hours with the heaters operating; b.
At least once per 16 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:
MILLSTONE - UNIT 3 3/4 9-13 Amendment No. J E,105 0327 l
l
-4 AEFUELING OPERATIONS e
BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The ~ restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the safety analysis.
If4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEM The limitations on the Fuel Building Exhaust Filter System ensure that all radioactive iodine released from an irradiated fuel assembly and storage pool water
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will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the heaters coerating 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.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
ANSI N510-1980 will be used as a procedural guide for surveillance testing. The filtration system removes radiciodine following a fuel handing or heavy load drop accident. Noble gases would not be removed by the system.
Other radionuclides would be scrubbed by the storage pool water.
8 days. After 60 days decay time, th:ere Iodine-131 has the longest half-life:
is essentially negligible iodine and filtration is unnecessary.
3/4.9.13 SPENT FUEL POOL - REACTIVITY The limitations described by Figure 3.9-1 ensure that the reactivity of fuel assemblies introduced into Region II are conservatively within the assumptions of the safety analysis.
Administrative controls have been developed and instituted to verify that the enrichment and burn-up limits of Figure 3.9-1 have been maintained for the fuel assembly.
3/4.9.14 SPENT FUEL P0OL - STORAGE PATTERN The limitations of this specification-ensure that the reactivity conditions of ~ the Region I storage racks and spent fuel pool k,n will remain less than or equal to 0.95.
The Cell Blocking Devices in the 4th location of the Region I storage racks are designed to prevent inadvertent placement and/or storage of fuel assemblies in the blocked locations. The blocked location remains empty to provide the flux trap to maintain reactivity control for fuel assemblies in-adjacent and diagonal locations of the STORAGE PATTERN.
STORAGE PATTERN for the Region I storage racks will be established and expanded from the walls of the spent fuel pool per Figure 3.9-2 to ensure definition and control of the Region I/ Region II boundary and midimize the number of boundaries where a fuel misplacement incident can occur.
MILLSTONE - UNIT 3 8 3/4 t-3 Amendment No. M.m 5 ene
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