ML20198H834
| ML20198H834 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/28/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198H840 | List: |
| References | |
| NUDOCS 8605300573 | |
| Download: ML20198H834 (6) | |
Text
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e ar UNITED STATES NUCLEAR REGULATORY COMMISSION g
g r7 p
WASHINGTON, D. C. 20555
%,.....j ROSTON EDIS0N COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-35 1
1.
The Nuclear Reaulatory Comission (the Commission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated February 28, 1986, complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 9
The facility will operate in conformity with the application, the provisions of the Act, and the rules and reaulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endancering 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; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operatina License No. DPR-35 is hereby amended to read as follows:
8605300573 96052 PDR ADOCK 05000 3
P P
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR T NUCLEAR REGU ATOR' COMMISSION
\\-
su John
. Zwolinski, Director 1
BWR P oject Directorate #1 Divis on of BWR Licensina 1
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
May 28,1986.
I
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O e-i
d ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise the Appendix A Technical.. Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
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REMOVE INSERT 128 128 128A 128A 139 139 i
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FIGURE
- 3. 6.1 PILGRIM REACTOR VESSEL PRESSURE-TEMPERATURE LIMITS HYDROSTATIC AND LEAK TESTS i
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O 40 80 lio 16 0 200 240 TE MPER ATURE
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AMENDMENT N O. 82, 94 12 8
FIGURE
- 3. 6. 2_
PILGRIM REACTOR VESSEL PRESSURE-TEMPERATURE LIMITS SUBCRITICAL/ CRITICAL HEAT UP a COOL. DOWN RPV WALL
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1 40 80 120 16 0 200 240 TE M PER ATURE
(*F)
AMENDMENT NO. 82, 94 128A
Bases:
3.6.A and 4.6.A Thermal and Pressurization _ Limitations (Cout'd)
The reactor coolant syttem is a priaary 'narr.ler a9sinst the release'of f.lssion products to the environs.
In order to provide assurance that this barrier is maintained at a high degree of integrity, restrictions have been placed on the operating conditions to which it can be ' subjected.
Appendix G to 10CFR50 defines th' te'mperature-pressurization restrictions for e
hydrostatic and leak tests, presturization, and critical operation.
These limits have teen calculatGd f6r Pilgrim &nd are contained in Figures 3.6.1 and 3.6.2.
For Pilgrim pressure-tempe~rature ~estrictions, two locations in the reactor r
vessel are limiting.
The clQsurB r.egioS Controll at lower pressures and the beltline controls at higher pres $ures.
The nit-doctility transition (NDT) teeperature is defined as the temperature below which ferritic steel breaks in a brittle rather than ductile manner.
Radiation exposure from fast neutrons (>1 mev) above about 10 nyt may shift the NDT temperature of the vessel Cetal above the initial value.' Impact tests from the first paterial 3pevel} lance capsule removed from the reactor vessel have estabitshed the magnitude of the RT=or shift for the beltitoe.
The shift, whicn is greatest for the weld metal, is tabulated below for various fluence levels:
RP1/ Wall Fluence _(1/4T)
RTyor 2.5 x 10 n/cm*
61*F 3.4 x 10*' n/cm' 68*F Neutron flux wires and samples of vessel material are Installed in the teactor vessel adjacent to the vessel wall at the core midplane level, The wires and samples will be periodically removed and tested to experimentally verify tne
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values used for ' Figures 3.6.1 and 3.5.2.
The withdrawal schedule of Table 4.6.3 has been established as required by 10CFRSO, Appendix P..
The pressure-tecperature limitations of Figures 3.6.1 and 3.6.2 applicable to the beltline reflect an tnttial RT.or of O'F.
This. initial value is based J
Amendment No. 'd2. 94 139
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