ML17053C633

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Amend 43 to License DPR-63,revising Tech Specs to Ensure Control Rod Drive Sys Operability & Reflect Mods to Scram Discharge Sys Now Underway
ML17053C633
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/13/1981
From: Ippolito T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17053C634 List:
References
NUDOCS 8105280079
Download: ML17053C633 (12)


Text

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NI'AGARA NOHAMlC POMER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No.

DPR-63 1.

The Nuclear Regulatory Commission /the Commission} has found that:

A.

The applications for amendment by Ni'agara Mohawk Power Corporation (the licensee} dated October 15, 1980 and Apri'1 1, 1981, comply 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; C;

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; 1C There is reasonable assurance (i} that'he--activities authorized by this amendment can be conducted without endangering the health and safety of the pu5lic, and (ii'} that such activities will be con-ducted 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Faci lity Operating License No.

DPR-63 is hereby amended to read as follows:

(2) Technical S ecifications The Technical Specifications contained in Appendices, A and B, as revised through Amendment No. 43, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 13, 1981 Thomas

. Ippolito, Chief Operating Reactors Branch 82 Division of Licensing

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ATTACHMENT TO LICENSE AMENDMENT NO.

43 FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:

Remove 117 119 191 tneert 117 119 191 rt' ttM

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT c.

If Specifications 3.2.7a and b above are not met, initiate'ormal orderly shutdown within one hour and have reactor in the cold shutdown con-dition within ten hours.

c.

At least twice er week the feadwater and ma n-steam-one power-operated iso-lation valves shall be exercised by partial closure and subsequent re-opening.

d.

At least once er uarter the scram dis-c arge system air operated vent and drain valves shall be fully closed and reopened.

117

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LIHITING CONDITION FOR OPERATION Table 3.2.7 (Continued)

REACTOR COOLANT SYSTEH ISOLATION VALVES Line or S stem No. of Valves Each Line Location Relative to Primary Containment Normal Position Haximum Action on Initiating Signal Oper.

Time Initiating (All Valves Have Reactor Head S ra Une L)nu L I el<i I oison Control liuu Drive H draulic

)U<<e L lno Inside Outside Inside Outside Inside Outside Closed Self Act. Ck.

R.H.P.O.

Self Act. Ck.

Self Act. Ck.

Self Act. Ck.

Self Act. Ck.

30 Scra<n I)ischarge System Vent

$ 0n<. T i<f<!)

Scram I) lscharge Syste<n Drain IUn'u <.)<<e)

Outside Open A.I.A.O.

Outside Open A.I.A.O.

p

  • A.I.P.O. - Automatically I itiated Power Operated
  • R.H.P.O. - Remote Hanual Power Operated A.I.A.O. - Automatically Initiated Air Operated

, 10 10 Close Close High neutron flux, High reactor pressure, High primary contain-ment pressure, Low water. level in the re-

actor, High level ln the scrmn discharge volu<ne, Low vacu<nn in condenser, High radiation in main stean< line, Closure of main steam isolation
valves, Loss of nor<nal and reserve AC power.

119

Table 3.6.2a INSTRUMENTATION THAT INITIATES SCRAM Limitin Condition for 0 eratin Parameter Minimum No. of Minimum No.

Operable Instrument of Tripped or Channels per Operable Operable

~Ti S

t Ti S

Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable 0

e O

Ol S-4 A$

QJ Vl QC Vl OC'1)

Manual Scram (2)

High Rector Pressure (3)

High Drywell Pressure (4)

Low Reactor Water Level (5)

High Water Level Scram Oischarge Volume 1000 psig 3.5 psig 53 inches (Indicator scale)

< 45 gal.

X X

X X

X X

X (a)

(a)

X X

X (b)

X X

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