ML20213A027
| ML20213A027 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/09/1987 |
| From: | Rajender Auluck Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213A029 | List: |
| References | |
| NUDOCS 8704270349 | |
| Download: ML20213A027 (4) | |
Text
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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated October 2, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; 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 been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.100, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 30 days after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION CL{cdv Mk t
Rajender Auluck, Project Manager BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: APR 9 1337 1
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LIMITING CONDITIONS FOR OPERATION SURt!EILLANCE REQUIREMENTS 9
3.11 REACTOR FUEL ASSEMBLY 4.11 REACTOR FUEL ASSEMBLY Applicability:
Applicability The Limiting Conditions for Operation associated with fuel The surveillance requirements rods apply to those parameters apply to the parameters which which monitor the fuel rod the fuel rod operating operating conditions.
conditions.
1 Objective:
Objective:
The Objective of the Limiting Conditions for Operation is to The Objective of the assure the performance of the Surveillance Requirements is to fuel rods.
specify the type and frequency of surveillance to be applied to the fuel rods.
Specifications:
Specifications A.
Average Planar Linear Heat Generation Rate (APLHGR)
A.
Average Planar Linear Heat Generation Rate (APLHGR)
During power operation with both recirculation pumps operating, The APLHGR for each type of the APLHGR for each type of fuel fuel as a function of average as a function of average planar planar exposure shall be exposure shall not exceed the determined daily during reactor applicable limiting value shown operation at >25% rated thermal in Figures 3.11-1 through power.
3.11-7.
The top curves are applicable for core flow greater than or equal to 90% of rated core flow. When core flow is l
less than 90% of rated core flow, the lower curves shall be limiting.
If at any time during operation it is determined by normal surveillance that the limiting value for APLHGR is being exceeded, action shall be j
initiated within 15 minutes to i
restore operation to within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
Amendment No. E9,100 205A
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i MAPLHGR Versus
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Planar A verage Exposure 1
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13 aximum 12.3
- - Core Flow >,- 90% rated 1
Average t
12.1
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Planar 12;0 i
Linear Heat 12 0- Core Flow < 90% rated Rate
/ft) 11 -p 11.4 3
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200 8.6 8
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0 5000 10000 15000 20000 25000 30000 35000 40000 45000 Planar Average Exposure (MW d/l)
Figure 3.11-7
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