ML20213G911
| ML20213G911 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/13/1987 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213G907 | List: |
| References | |
| NUDOCS 8705190025 | |
| Download: ML20213G911 (5) | |
Text
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[po osog'o UNITED STATES E "* 3 # ( [,j NUCLEAR REGULATORY COMMISSION g
/. E W ASHINGTON, D. C. 20555 s
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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Yankee Atomic Electric Compnay (the licensee) dated October 9, 1986 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 ;;
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 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 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-3 is hereby amended to read as follows:
g5190025870513 ADOCK 05000029 p
'. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.105, 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 Victor Nerses, Acting Director Project Directorate I-3 Division of Reactor Projects, I/II Attachtrent:
Changes to the Technical Specifications Date of Issuance: MAY 13 W37 i
/'"" '%['t UNIT ED STATES e-.
NUCLEAR REGULATORY COMMISSION k
j WASHINGTON, D. C. 20555 e
ATTACHMENT TO LICENSE AMENDMENT AMENDME!J NO.105 TO FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by reinoving the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Pages Insert Pages 3/4 3-8 3/4 3-8 3/4 3-10 3/4 3-10 l
l
bg TABLE 4.3-1
'?g REACTOR PROTECTIVE SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL MODES IN WHICH CHANNEL.
CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED III 1.
Manual Reactor Trip NA NA S/U HA 2.
Power Range, Neutron Flux and Intermediate Power Range, I2)
Ib)
M(6)
Neutron Flux S
D
,R 1, 2 and
- 3.
Intermediate Range, Neutron Flux, a2 High Startup Rate S
R(5)
M 1, 2 and *
[
4.
Source Range, Neutron Flux S
R(5)
II)
S/U 2, 3, 4, 5 and
- I4)
M(3) 5.
Low Main Coolant Flow (SGaP)
S R
g 6.
Low Main Coolant Flow, Systems A and B (MC Pump Current)
S R
M 1
k 7.
High Main Coolant System Pressure S
RI4)
M 1, 2 I4I 8.
Low Main Coolant System Pressure S
R M
1, 2
[
9.
High Pressurizer Water Level S
RI4)
M(3) 1, 2 IN
- 10. Low Steam Generator Water Level S
R M
1 b
A
TABLE 4.3-1 (Continued) a NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in the previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER, at least 3 times per week with a maximum time interval of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
(3)
When shutdown longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed in the previous 31 days.
(4)
Known pressure applied to sensor.
(5)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(6)
Low trip setpoint verification excluded. The Channel Functional Test, performed on a monthly basis, provides all the elements of a calibration that can be done at power.
YANKEE-ROWE 3/4 3-10 AmendmentNo.jdI,Ef,105 i
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