ML17319B144
| ML17319B144 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/30/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319B145 | List: |
| References | |
| NUDOCS 8201210326 | |
| Download: ML17319B144 (8) | |
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l UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No.
DPR-58 1.
The Nuclear Regulatory Commission
(..the Commission) has found that:
A.
B.
C.
The request for amendment by Indiana and Michigan Electric Company (the licensee) dated August 14, 1981, as supplemented by letter dated August 17, 1981, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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, and paragraph 2.C.QJ of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
(g) Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
'50, are hereby incor-porated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective August 18, 1981.
THE N
E R
GULATORY COMMISSION Steven A+Yarga, Ch'perating Reactors anch.
81 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
NOV 3 0 1981
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A as follows:
l-l Insert Pa es l-l 1-1 a 1-2~
- Added for convenience
1.0 DEFINITIONS DEFItiED TERMS 1
1.1 The DEFINED TERMS of this seccion appear in ccpitalize'd type. and are applicable throughout these Technical Specifications.
THERtriAL POWER 1.2 THEPPiAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THEPPiAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate'.to the reactor coolant of 3391 MWi.
-OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combina-'ion of core reactivity condition, power level and averaoe 'reactor coolant temperature speci fied in Table 1.1.
ACii0l' r.'
I ON s; c / 1 be:.hose cddii t iolla 1 rcoUl rei ien s
5 pcc i i ed as col ol 1 c rv st E. e
~ 's '0 each princ ipl c spE'cl f1 cation
- c. id shell bc pal t of thE'peCl fi Cct, ionS OPER'BLE - OPERABILITY 1.6 A sys.em, subsystem, train, comporent or oevice shall be OPERABLE or have OPERABILITY when it is capable o<
perfor
.iing its specified function(s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation,
- controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are requir ed for the system, subsystem,
- train, component or device to per orm its unction(s) are also capable of performino their related support function(s).*
+On Auoust 14, 1981 and Auoust 17, 1981 the following safety-related
.cabinets,.
motor control centersand switchgear were discovered to have inadequate seismic su ppol I.
( a )
600V motor con rol cen i ers, Unit '
only number s MiCC-2-AMi-A and D,
(b) 4 YV Switchoear Busses/Cabinets numbers Tll A,B,C, and D for Unit 1
and T21 A,B,C, and D for, Unit 2, and (c) 600V Switchgear Buses/Cabinets numbers ll A,"~C and D for Unit 1
and 21 A,B>C, and D for Unit 2.
The above equipment sha.l
~be declared operable providing the
>ollowing restric.ions are met:
C.
COOK -
UNI.T 1
l-l Amendment No. 50
Cor tinued (1) Reactor pover shall be decreased until either 60', reactor po"!er is reached or temporary bracing of one train of eouipment is completed.
(2) the temporarv bracing is not installeo within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> a=ter reaching 60.
Dower, further approval or operation must be obtained from the NRC Staff.
(3)'he unit may be operated up to 1 00r. power after temporary bra cino i s i nsta1 1 ed on one train of eouipment.
However, the second train must be properly braced within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the first train beino braced.
(4) Permanent modifications to provide'degUate seismic support for the equipment involved shall be completed by August 21, 1981:
D.
C.
COOK - UNIT 1 1-1 a Amendment No. 50
DEFINITIONS REPORTABLE OCCURRENCE 1.7 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9. 1.8 and 6.9.1.9.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment auto-matic isolation valve system, or
- b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification
- 3. 6. 3.1.
1.3.2 All equipment hatches are closed and sealed, 1.8.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3, and 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
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 and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
D. C.
COOK - UNIT 1 1-2 Amendment No. 23