ML20062B734
| ML20062B734 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/22/1990 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062B733 | List: |
| References | |
| NUDOCS 9010260105 | |
| Download: ML20062B734 (6) | |
Text
_
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o, UNITED 8TATES i
NUCLEAR REGULATORY COMMISSION 1
e 5
.t WASHINGT oN, D. C. 20656
'+4..... $
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CONNECTICUT YANKEE ATONIC POWER COMPANY DOCKET NO. 50-213 f
i HADDAM NECK PLANT AMENDhENT TO FACILITY OPERATING LICENSE
[
Amendment'No.132 License No. DPR-61 l
t 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated August 25, 1990, and as supplemented in a letter dated August 29, 1990, 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 appli-cation, 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 i
endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with-the Commission's regulations; i
D.
The issuance of this amendment will-not be inimical to the u
)
common defense and security or to the health and safety of l'
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.-
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. OPR-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications _ contained in Appendix A, as revised through_ Amendment No.132, are hereby incorporated in the license.
The licensee shall operate the facility in i
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be I
implemented within 30 days of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects - I/II 5
Office of Nuclear Reactor Regulation
~
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 22, 1990 f
a 6
l ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET No. 50-213 l
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 J
1 3/4 3-15 3/4 3-15 3
l 3/4 3-19 3/4 3-19 l
i 3/4 3-21 3/4 3-21
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TABLE 3.3-2 (Continued)
. I l
t l-g ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTAT;0N i
o l
-]
MINIMUM l
TOTAL NO.
CHANNELS CHANNELS-APPLICABLE FUNCTIONAL' UNIT OF CHANNELS TO ACTUATE OPERA 8LE MODES ACTION
^
i n
a 3.
~ Auxiliary Feedwa}er*
I I
a.
Wide Range Stm. Gen. Water Level--
Low
- 1) Four Loops 8
2 Channels 8
1(a)(b) 21
[
Operating in any one train L
2)fThreeLoops 6
2 channels 6
1(a)(b) --
. 26 Operating in any one train R.
I *)
26 l
I b.
Trip of All Main 1/ pump 1 from each 1/ pump l.
{
'Feedwater Pumps pump
~4.-
Emergency Bus Undervoltage
~
1 a.?4.16 kV Bus Under-3/ bus 2/ bus 2/ bus.
1, 2,-3, 4 24 l
voltage-level 1:
'1 b..E4.16 kV Bus Undervoltage-
_2/ bus 2/ bus 1,-2,.3, 4 24-
.3 l Level 2.
3/ bus L
~@-
'c.
4.16 kV'. Bus Undervoltage-
..3/ bus
'2/ bus 2/ bus 1, 2 24
[
Level'3
?
For Cycle 16 operation only, OPERA 8ILITY of automatic initiation of auxiliary feedwater. (AFW) is defined as
~O including (1) credit for. operator action:to adjust AFW to full required flow following automatic initiation and 5
(2)' reliance on the control air system to ensure. successful automatic AFW initiation. Modifications will be
- implemented by the end of the Cycle 16 refueling ~ outage, prior to startup for Cycle 17, to remove reliance on:
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- operator action and the control air system for successful automatic initiation of AFW.
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i _.
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.%,.,g.,,
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i TABLE 3.3-3
-.)
f j'
B EtlGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS
.o E
l M-FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE n
I
.x
. Safety Injection (Reactor Trip, 1.
Start Diesel Generators, l
Containment Isolation).
I a.
Manual Initiation M.A.
N.A.
b.
Containment Pressure--High 54.7 psig
$5.0 psig c.
_ Pressurizer Pressure--Low 21720 psig 11700 psig 2.
Steam Line: Isolation i
R a.
Steam Flow in Two Steam-
$108% of full *
<110% of full
- Lines--High steam flow.
steam flow.
V l!
g 3.
- Auxiliary Feedwater**
-a.-
. Steam Generator Water-247% of wide.
245% of wide Level--Low range instrument range instrument span.
span.
b.
Trip of All Main Feedwater Pumps N.A.
N.A.
4j
. For Cycle 16 operation only, OPERABILITY of automatic initiation of auxiliary feedwater (AFW)~ is defined as including (1) credit for operator action to adjust AFW to full required flow following automatic initiation and a
(2) reliance on the control air system to ensure successful automatic AFW initiation. Modifications will be
' implemented by the end.of the Cycle 16 refueling outage, prior to startup for Cycle 17, to remove reliance on g
. operator action:and the control-air' system for.suc;essful automatic initiation of AFW.
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w r-
+ + ~ - - - - - - - - - - - - - - - - - - - - - - - - - -
._aa n..,,,,
TABLE 4.3-2 b'
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g
SURVEILLANCE REQUIRENENTS MiR TRIP ANALOG ACTUATING MODES FGR CHANNEL
-DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL SURVEILLANCE CHANNEL CHECK CALIBRATION TEST TEST IS REQUIRED FUNCTIONAL UNIT 1.
Safety Injection (Reactor Trip, Start Diesel-Generators, Containment Isolation) a.
Manual Initiation N.A.
N.A.
N.A.
R 1,2,3 b.
Containment Pressure-D R
SW.
N.A.
1, 2, 3 R
. iligh Y-c.
Pressurizer Pressure-S
'R SW N.A.
1, 2, 3 5
Low 2.
Steam Line Isolation a.
Steam Flow in Two S
R R
'N.A.
1, 2, 3 Steam Lines-High 7
.3.
Auxill'ary Feedwater*
l g.
-a.
Steam Generator Water-
-S R-iM N.A.
1
- Level-Low F
- b. ' Trip of All Main:
N.A.-
N.A..
N.A.
R-1 Feedwater Pumps R;'
For Cycle 16 operation only, OPERABILITY of automatic initiation of auxiliary feedwater (AFW) is defined as
- =~
including (1) credit: for operator' action to adjust AFW to full. required flow following automatic initiation and C
(2)-reliance on the control' air system.to ensure successful automatic AFW initiation.. Modifications will be implemented-by-the end of the Cycle 16 refueling outage, prior to startup for Cycle 17, to remove reliance on
- operator ~ action 'and the control air system for successful automatic initiation of AFW.
- =-
- -.