ML20212M194
| ML20212M194 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/27/1987 |
| From: | Rajender Auluck Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212M198 | List: |
| References | |
| NUDOCS 8703110268 | |
| Download: ML20212M194 (4) | |
Text
py w
~..:...... s,
.. a.
.u._....-.....u-.~..
/
UNITED STATES I
NUCLEAR REGULATORY COMMISSION g
5 wAsmuoTow.o.c. zones
- s.,*ses*/
BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licenseel dated September 5, 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.
Thereisreasonableassurance(1)thattheactivitiesauthori7ed 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 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 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 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:
P I
v
--.---,--wn-+--m.-r------
---p,
,--m-,,,
,--------www,---,--,-,---n-,----,--,v---r--w-r,-
---m--,,-
E
_........_..;....~.;....
. B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 98 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 EMM Rajender Auluck, Project Panager BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 27, 1987
.-,.a....x.....
.w.
.... u.\\..
% ~;
ATTACHPFNT TO LICENSE AMENDMENT NO. 98 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 papes are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 206m 206m I
yw c
.~u...
s... :
-...u. -~ a-. ~.
..~.
o 5.0 MA.10R DESIGN FEATURES 5.1 SITE FEATURES Pilgrim Nuclear Power Station is located on the Western Shore of Cape Cod Bay in the Town of Plymouth, Plymouth County, Massachusetts.
The site is located at approximately 41'51' north latitude and 70'35' west longitude on the Manomet Quadrangle, Massachusetts. Plymouth County 7.5 Minute Series (topographic) map issued by U.S. Geological g Survey. UTH coordinates are 19-46446N-3692E.
The reactor (center line) is located approximately 1800 feet from the nearest property boundary.
5.2 REACTOR i
i A.
The core shall consist of not more than 580 fuel assemblies of 8x8 (63 fuel rods) P8x8R (62 fuel rods), and BP8x8R (62 fuel rods).
8.
The reactor core shall contain 145 cruciform-shaped control rods.
The control: materials shall be either boron carbide powder (8 C) compa9ted to approximately 70% of theoretical 4
density or a combination of boron carbide powder and solid hafnium.
5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2.2 of the FSAR.
The appilcable design codes shall be as described in Table 4.2.1 of the FSAR.
5.4 CONTAINNENT A.
The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FSAR.
The applicable design codes shall'be as described in Section.12.2.2.8 of the FSAR.
8.
The secondary containment shall be as described in Section 5.3.2 of the FSAR.
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.
Amendment No, M, 78,98 206m