ML20031F607
| ML20031F607 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/02/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031F608 | List: |
| References | |
| NUDOCS 8110200212 | |
| Download: ML20031F607 (3) | |
Text
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NUCLEAFI REGULATORY COMMISSION 5
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~ BOSTON EDISON COMPANY DOCKET N0. 50-293 PILGRIM NUCLEAR POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-35 1.
The Nuclear Regulatory Commission. (the Commission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated September 22, 1981 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.
Tne facility will operate in confomity with the app 1,1 cation, 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 f.ealth 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-35 is hereby.
amended to read as follows:
3.B Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."
MUND 0
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2 3.
This license Amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 2,1981 I
D 9
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ATTACHMENT TO LICENSE AMENDMENT N0. 49 FACILITY OPERATING LICENSE N0. DPR-35 DOCKET NO. 50-293_
Revise Appendix A as follows:
Remove page 204A and insert identically numbered page.
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,e 3.10 BASES B.
Core Monitorin*;
The SRM's are provided to monitor the core during ceriods of station shutdown and to guide the operator during refueling operations and station startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that quadrant during such alterations. The requirement of 3 counts per second provides assurance that neutron flux is being monitored ard insures that startup is conducted only if the source range flux level is above the mini.num assumed in the contre; rod drop accident.
The limiting conditions for operation of the SRM subsystem of the Neutron Monitoring System are derived from the Station Nuclear Safety Operational Analysis (Appendix G) and a functional analysis of the neutron monitoring system. The specification is based on che Operational Nuclear Safety Require-ments in subsection 7.5.10 of the Safety Analysis Report.
A spiral unloading pattern is one by which the fuel is in the outermost cells (four fuel bundles surrounding a control blade) is removed first. Unioading continues by removing the rem ing outermost fuel cell by cell. The center cell vill be the last removed. iSpiral loading is the reverse of unloading.
Spiral unloading and reloading vill preclude the creation of flux traps (moderator filled cavities surrounded on all sides by fuel).
Du' ring spiral unloading, the SRM's shall have an initial count rate of 13 cps with all rods fully inserted. The count rate vill diminish during fuel re= oval.
Under the special condition of complete spiral core unloading, it is expected that the :ount rate of the SRM's will drop belov 3 cps before all of the fuel is unloaded.
Since there vill be no reactivity additions, a lower number of counts vill not present a hazard. When all of the fuel has been removed to the spent fuel storage pool, the SRM's vill no longer be required.
Requiring the SRM's to be operational prior to fuel removal assures that the SRM's are operable and can be relied on even when the count rate may go below 3 cps.
During spiral reload, SRM operability will be verified by using a portable
' external soorce every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until the required amount of fuel is loaded to maintain 3 cps. As an altetnative to the above, up to two fuel assemblies vill
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be loaded in different cells containing control blades around each SRM to obtain the required 3 eps. Until these assemblies have been loaded, the 3 cps require-ment is not necessary.
C.
Spent Fuel Pool Water Level To assure. that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established.
i The minimum water level of 33 feet is established because it would be a significant change frcxn the normal level (-1 foot) and is well above the level to assure adequate cooling.
During the 1981 refueling outage, prior to initiating spiral unloading, the l
central controlled tell will be removed to facilitate inspection of the Core i
Spray Spargers.
204A I
Amendment No. 49
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