ML17318A776
| ML17318A776 | |
| Person / Time | |
|---|---|
| Site: | Cook  (DPR-74-A-019, DPR-74-A-19) |
| Issue date: | 05/13/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17318A777 | List: |
| References | |
| NUDOCS 8005280186 | |
| Download: ML17318A776 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D, C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-.316 DONALD C.
COOK NUCLEAR PLANT UNI'T N0..2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
19 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee}
dated November 2, 1979 as supplemented on December ll, 1979 and March 18, 1980 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 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the coraIIon 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 I
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-74 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
1 9, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
In addition, license condition 2.C.(3)(i) "Leak Rate Testing of Containment Isolation Valves" and 2.C.(3)(m),"600 Volt Containment Power Penetration" are deleted.
4.
This license amendment is effective as of the date of its issuance.
FO THE NUCLEAR REGULATORY COMMISSION
Attachment:
I'hanges to the Technical Specifications Date of Issuance:
May 13, 1980 even A.
Ch perating Reactors nc Division of Licensing
ATTACHMENT TO LICENSE AMENDMENTS 0 AMENDMENT NO.
19 TO FACILITY OPERATING LICENSE NO.
. DOCKET NO. 50-316 Revise Appendix A as follows:
~RP 2-7 2-8 2-9 3/4 2-16 Insert Pa es 2-7 2-8 2-9 3/4 2-16
n A
Clo yc NOTE 1:
TABLE 2.2-1 (Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION Overtemperature hT
< hT
[K1-K2 1
(T-T )+K3(P-P )-fl(AI)]
1+t S
'~s where:
aT0 s
P Pr 1+~1 S T~>s 1
2 Indicated'hT at RATED THERMAL POWER Average.temperature,
'F Indicated T
at RATED THERMAL POWER 573F
'vg Pressurizer
- pressure, psig 2235 psig (indicated RCS nominal operating pressure)
The function generated by the lead-lag controller for T dynamic compensation avg Time constants utilized in the lead-lag controller for T vl = 33 secs, avg a
~2
= 4 secs; Laplace transform operator
n CD CD I
TABLE 2.2-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION Continued
= 1.334 Kl K2
- 0. 01607 K3
= 0.000744 Operation with 4 Loops Operation with 3 Loops Kl
= 1.116 KZ
= 0.01607 K
= 0.000744 3
M I00 CL B
and f (dI) is a function of the indicated difference between top and bottom detectors of thL power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for q
- q between - 40 percent and + 3 percent, fl (hI) = 0 (wherh q
knd q aie percent RATED THERMAL POWER in the top and bottom halves of'he cI)re respectively, and qt + qb is total THERMAL POWER in percent of RATEO THERMAL POWER).
(ii) for each percent that the magnitude of (q
- q) exceeds
- 40 percent, the aT trip setpoint shall be automatical y r ehuced by 'I.g percent of its value at RATEO THERMAL POWER.
(iii) for each percent that the magnitude of (q
- q) exceeds
+ 3 percent, the bT trip setpoint shall be automaticalf'y reduced by 2.2 percent of its value at RATEO THERMAL POWER.
0
Cl TABLE 2.2-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION Continued)
Note 2:
Overpower eT
< eT [Ke-K< ~+S T KO (T-T")-f>(e))]
"3'here:
AT
=
Indicated hT at rated power 0
T
=
Average temperature,
'F T"
=
Indicated T
at RATED THERHAL POWER
< 573 8'F avg K4
=
1. 078 K5
=
0.02/'F for increasing average temperature and 0 for decreasing average tempera tur e K6 0.00197 for T > T"; K6 = 0 for T
< T" t3S I4t S
The function generated by the rate lag controller for Tavg 3
dynamic compensation Time constant uti 1 i zed in the rate lag control 1 er for T
~3
= 10 secs.
S
=
Laplace transform operator O
Note 3:
f2(~I) =
0 for all b,I The channel's maximum trip point shall not exceed 4 percent.
its computed trip point by more than
POWER DISTRIBUTION L IMITS NB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:
a.
avg'.
Pressurizer Pressure.
APPLiCABILITY:
MODE 1
ACTIDN:
With any of the above parameters exceeding its limit, restore the param-eter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5'.l of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE(UIREMENTS 4.2.5 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D.
C.
COOK - UNIT 2 3/4 2-15
TABLE 3.2=1 DNB PARAMETERS PARAMETER Reactor Coolant System T.
Pressurizer Pressure LIN ITS 4 Loo s In 0 er'ation
< 578 oF
> 2220 psia+
3 Loo s In 0 eration
< 570 oF
> 2220 psia*
- Limit not applicbale during either a
THERMAL POMER ramp increase in excess of 5% RATED THERMAL POMER per minute or a THERHAL POMER step increase in excess of 10$
RATED THERMAL POMER.