ML20205E273
| ML20205E273 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/09/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20205E277 | List: |
| References | |
| DPR-35-A-090 NUDOCS 8510170253 | |
| Download: ML20205E273 (4) | |
Text
.
OM4 9'o UNITED STATES 08 g
NUCLEAR REGULATORY COMMISSION o
O p
WASHINGTON, D. C. 20555 e
\\...+/
BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated June 18, 1985, 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 (1) 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 l
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 l
have been satisfied.
l l
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 3.B of Facility Operating License No. DPR-35 is hereby l
amended to read as follows:
l l
8510170253 851009 I
PDR ADOCK 05000293 I
P ppg
.ea
--e,,
--n--
. B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 90, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with he Technical Specifications.
3.
This license amendment is effective as of 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 9,1985 l
9 f -
i
ATTACHMENT TO LICENSE AMENDMENT NO. 90 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 j
Replace the following page of the Technical Specifications with the enclosed 1
page. The revised page is identified by amendment number and contains a vertical line indicating the areas of change.
Remove Insert i
47 47 4
4 e
&e l
e PNPS
. TABLE 3.2.8 INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of Operable Instrument Channels Per Trip System (1)
Trip Function Trip level Setting Remarks 2
Reactor Low-Low Water at or above -49 in.
1.
In conjunction with Low l
Level Indicated level (4)
Reactor Pressure, initiates Core Spray and LPCI.
2.
In conjunction with High Drywell Pressure, 120 second time delay and LPCI or Core Spray pump interlock initiates Auto Blowdown (ADS).
3.
4.
Initiates starting of Diesel Generators.
~
2 Reactor High Water Level
<+43" indicated Trips HPCI and RCIC turbines.
Tevel I
Reactor Low Water Level 2307" above vessel Prevents inadvertent operation (Inside shroud) zero (approximately of containment spray during 2/3 core height) accident condition.
2 Containment High Pressure 1 < p < 2 psi ~g Prevents inadvertent operation
~
of containment spray during accident condition.
Amendment No. 90 47
-