ML20097B794
| ML20097B794 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/04/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20097B795 | List: |
| References | |
| DPR-35-A-078 NUDOCS 8409140151 | |
| Download: ML20097B794 (8) | |
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~8 UNITED STATES 8
N NUCLEAR REGULATORY COMMISSION t
.y WASHINGTON, D. C. 20555 k;4.....l BOSTON EDISON COMPANY DOCKET N0. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 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 December 28, 1983, as supplemented February 21, and July 12, 1984, 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 Commissien's regulations; D.
The issuance of this cmendment will not be inimical to the common defense and security or to the health and safety of the public; ar.d 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 Operating License No. DPR-35 is hereby amended to read as follows:
l B409140151 840904 PDR ADOCK 05000293 P
. B Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, 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 THE NUCLEAR REGULATORY COMMISSION
- Y.{ s
.t Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 4,1984 t
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ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines' indicating the areas of change.
Remove Insert 2058-2 205B-2 205E-4 205E-4 205E-5 205E-5 205E-6 205E-6 206m 206m a
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TABLE 3.11-1 OPERATING LIMIT MCPR VALUES A.
MCPR Operating Limit from Beginning of Cycle (B0C) to BOC + 6000 MWD /T.
8x8 P8 x 8R/BP8x8R For all values of T 1.36 1.40 B.
MCPR Operating Limit from 80C + 6000 MWD /T to End of Cycle.
T 8x8 P8x8R/BP8x8R T<
0 1.38 1.40
- 0. 0 < T < 0.1 1.39 1.41 0.1 < T < 0.2 1.39 1.41
- 0. 2 < T < 0.3 1.40 1.42
- 0. 3 < T < 0.4 1.40 1.42 0.4 < T< 0.5 1.41 1.43
- 0. 5 < T <_ 0.6 1.41 1.43 0.6 < T< 0.7 1.42 1.44
- 0. 7 < T < 0.8 1.42 1.44
- 0. 8 < T < 0.9 1.43 1.45 0.9 <T < 1.0 1.43 1.45 i
y Amendment No. k, J, 78 2058-2 d
l FIGURE 3.11-4 f
MAXIMUM AVFRAGF PL ANAR LINFAR HPAT GENERATION RATE l
VERSUS i
PLANAR AVERAGE EXPOSURE j
,E FUEL TYPES P80RB265L and BPDRB265L 4>
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6 12 12,1 sk.I i.I CORE FLOW h 90% RATED il 11 ie, e
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CORE FLOW < 90% RAT E D 6i mm 10 Qego i
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O 4000 10,000 I!pOO 2q000 2pOO 3QOOO 3@000 40,000 I
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PLANAR AVERAGE EXPOSURE (MW cyt:,)
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l FIGURE 3.11 - 5
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MAXIMUM AVFRAGE PLANAR LINF AR HEAT GENERATION RATE ~
ia VERSUS i?
PLANAR AVERAGE EXPOSURE FUEL TYPES P80RB282 and BP80RB282 g
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PLANAR AVERAGE EXPOSURE (MW @)
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l FIGURE 3.1 l-6 y
MAXIMUM AVFRAGF PLANAR LINFAR HFAT GENFRATION RATE g
VERSUS l?
PLANAR AVFRAGE EXPOSURE A
l FUEL TYPES P80RB265H and BP8DRB265H N.
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,9 CORE FLOW 32 90% RATED l
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CORE FLOW 4 90% RATED 10/
10,2 mw gogo 9.7 95 2$
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SpOO IOpOO Ip0 2q000 2'pOO 3QOOO 3q000 40,000 T
8 PLANAR AVERAGE EXPOSURE (MW cj/t:,)
1 5.0 MAJOR 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, Plyniouth County 7.5 Minute Series (topographic) map issued by U.S. Geological Survey. UTM coordinates are 19-46446N-3692E.
The reactor (center line) is located approximately 1800 feet from the nearest property boundary.
5.2 REACTOR 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).
B.
The reactor core shall contain 145 cruciform-shaped control rods.
The control material shall be boron. carbide powder (BuC) compacted to approximately 70% of theoretical density.
5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2.2 of the FSAR.
The applicable design codes shall be as described in Table 4.2.1 of the FSAR.
5.4 CONTAINMENT A.
The principal design parameters for tWe 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.
B.
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 shali be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.
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Amendment No. [, 78 206m l
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