ML20141M880
| ML20141M880 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/19/1986 |
| From: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141M876 | List: |
| References | |
| NUDOCS 8602280806 | |
| Download: ML20141M880 (6) | |
Text
'f?
'o,,
UNITED STATES
!\\
NUCLEAR REGULATORY COMMISSION
' g s y.q W ASHING T ON, D. C. 20555
%.... /
+
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-61 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated October 31, 1985, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 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 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:
hN
[
P
4 (2) Technical Specifications i
The Technical Specifications contained in Appendix A as revised through Amendment No. 72, are hereby incorporated in the license.
l 1
The licensee shall operate the facility in accordance with the
{
Technical Specificati,ons.
3.
This license amendment is effective as of the date of its issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION Mt b 1.b j
Christopher I. Grimes, Director Integrated Safety Assessment i
Project Directorate Division of PWR Licensing - B I
l
Attachment:
Changes to the Technical Specifications
]
j Date of Issuance:
02/19/86 i
1 i
i l
1 i
i i
i i
I i
a
(
i t
1
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 72 l
FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
i l
REMOVE INSERT l
l 1-1 1-1 l
1-2 1-2 3-20d L
o 1.0 DEFINITIONS i
DEFINED TERMS 1.1 The DEPINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 1825 MWt.
OPERATIONAL MODE
~
1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
1.5 Not used.
OPERABLE - OPERAEILITY 1.6 A syste=, subsystem, train co=ponent or device shall be OPERABLE or have OPERABILITY when it is capable of perforr.ing its design function (s).
leplicit in this definition shall be the assu=ption that all attendant instrucestation, controls, electric power, cooling or seal water, lubrication or other required auxiliary equipment is also OPERABLE.
1.7 Deleted.
Amendment No. ), 72 l-1
~
DEFINITIONS CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 The containment automatic isolation valve system is OPERABLE.
1.8.2 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by OPERABLE containment automatic isolation valves, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured and locked in their closed positions.
NOTE: Normally-closed isolation valves listed in Table 3.11-2, which f ail closed on loss of power and are capable of being closed within 60 seconds of a containment isolation actuation signal (CIAS) by an operator utilizing normal control switches and normal position indication within the main control room may be opened for perionic testing.
1.B.3 All equipment hatches are closed and sealed, and 1.8.4 Each door in each air lock is closed and sealed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed and sealed.
CHATEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment of channel' output such that it responds, with acceptable range and accuracy 'to known values of the parameter which the channel measures.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip.
4 CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication with other indications derived from independent instrument channels measuring the same parameter.
... u.
Amendment No. 5, 72 1-2
e, Tchte 3.11-2 Non-Automatic Containment Isolation Valves valve Number, Containment Isolation valve Function Closure Tine, All Valves SS-SOV-150A containment Atomsobere 60 seconds SS-50V-150n Ilydrogen Analyzer and Post Accident Sampling SS-50V-150C Systen (PASS) Isolation SS-50V-150D l
l SS-Sov-151A SS-SOV-151B l
SS-507-151C SS-Sov-151D l
[
l i
t' l
1 l Amendment No. 72 3-20d I
~
_,.