ML20063M033
| ML20063M033 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/24/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063M036 | List: |
| References | |
| NUDOCS 9403080356 | |
| Download: ML20063M033 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
'Qf g WASHINGTON, D.C. 20555-0001
... +
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NVCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.-88 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated December 22, 1992, complies with tF.e standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 Comission; 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 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 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-80 is hereby amended to read as follows:
i 940300C356 940224 PDR ADTM 05000275 P
l 1 (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 88, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technfcal Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective after RTD bypass elimination and after Eagle 21 installation during the sixth refueling outage currently scheduled to begin March 1994, for Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION Jccbv d- "y Theodore R. Quay, Director Project Directorate V Division of Reactar Projects III/IV/V Office of Nuclear Heactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 24, 1994
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E UNITED STATES 5( [i j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001
....+
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 l
License No. DPR-82 l
l l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
l A.
The application for amendment by Pacific Gas & Electric Company l
(the licensee) dated December 22, 1994, complies with the I
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 (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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to read as follows:
0
F
.. (2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 87, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective after RTD bypass elimination and after Eagle 21 installation during the sixth refueling outage currently scheduled to begin September 1994, for Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION
,,[ wt6w JS >
7 Theodore R. Quay, Director' Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 24, 1994 l
.1 l
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO.'
87 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing 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. Overleaf pages are also included, as appropriate.
REMOVE
- INSERT 2-8 2-8 The page should not be removed until both units have completed the subject modification. TS page 2-8 provided in this amendment should be used in lieu of the same page provided in Amendment Nos. 84 and 83 dated October 7, 1993.
l
1Antt 7.7-1 l
k REACIOR TRIP 'iYSIEH IN51RlHENI AI!ON 1 RIP MII_ TINE O
IMI L_N0lMlQN3
^
5g NOTE 1:
OVERTEMPERATURf aT z
g ai (I
- T.S )
aT, K,-K, ( 1 + 1:5) [I
- j, g,gp p-)
s q
1+rS 1 + r,$
y'g, g )l g
v, w
=
Where: I + r,5
- Lead-lag compensator on measured ai I + r,5 N
- r., r,
= Time cc:.,tants utilized in the lead-lag controller for 4T. r, = 0 seconds, r = 0 seconds 3
aT,
= Indicated ai at RATED THERMAL POWER K,
= 1.2 X,
= 0.0182/*F ma 1 + r,5
= The function generated by the lead lag controller for T, dynamic compensation I + r,5 r,. r,
= Time constants utilized in the len-log controller for T,. r, = 30 seconds. r, = 4 seconds T
= Average temperature. 'F R
3 n
.=
n 9
TABLE 2.2-1 (Continued) 20 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
[
TABLE NOTATIONS n
Q NOTE 1:
(continued)
- z T'
= Nominal T at RATED THERMAL POWER y
K
= 0.000831/psig 3
e.n P
= Pressurizer pressure, psig P'
- 2235 psig (Nominal RCS operating pressure)
~
d S
- Laplace transform operator, s and f (AI) is a function of the indicated difference between top and between detectors of the power 3
range nuclear ion chambers; with gains to be selected based on measured instrument response during
'?
plant startup tests such that:
m (i) for q, - q, between -19% and +7%, f (AI) = 0 (where q and q, are percent RATED THERMAL POWER in l
the top and bottom halves of the co,re respectively, a,nd q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER).
- {
(ii) for each percent that the magnitude of (q - q3) exceeds -19%, the AT Trip Setpoint shall be
-gg automatically' reduced by 2.75% of its valu,e at RATED THERMAL POWER.
w g[
(iii) for each percent that the magnitude of (q, - gb) exceeds +7%, the AT Trip Setpoint shall be
,o automatically reduced by 2.38% of its value at RATED THERMAL POWER.
m' NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than Np 1.0% AT span.
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