ML17319B146
| ML17319B146 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/30/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319B145 | List: |
| References | |
| NUDOCS 8201210328 | |
| Download: ML17319B146 (9) | |
Text
~
~I,S ~aCI P
+
0 Cy I
0
~ %
O
+a*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No.
DPR-74 1.
The A.
B.
C.
D.
Nuclear Regulatory Commission (the Commission) has found that:
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 oper ate -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 5y 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; 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 require-ments have been satisfied.
8201210328, 81,1130.
-.,g,.:
',".CF,',;ADOCK 0500031 5
'CF';
II f
~
II
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 B, as revised through Amendment No.
35, 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.
F THE NUC AR GULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Operating Reactors B
nch 81 Division of Licensing Date of Issuance:
NOV 30 1981
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 35 TO FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:
Remove Pa es 1-1 2*
Insert Pa es 1-1 1-la 1-2*
- Added for convenience
1. 0 DEFINITIONS DE F I NE D T ERNiS 1.1 The DEFINED TERNS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERiNiAL POWER 1. 2 THERNiAL POWER s hcl 1 be the total reactor core heat trans fer rate to the reactor coolant.
RATED THERNiAL POWER 1.3 RATED THERNiAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3391 NWt.
0PERATIONAL NODE 1.4 An OPERATIONAL NODE shall correspond
'to any one inclusive combina-tion of core reactivity condition, power level and averaoe reac.or
'coolant temperature specified in Table 1.1.
'CiiGL'.
5 AC l!Gii s hia 1 1 be those Stc '." AtS tC'aCh pr1AC i pl SPeC i fiCctlOAS.
ccclo ic1 reoul l emic "its 5 Pcc1 f i ec as corol 1 arv e speciificction cAd shell be part of the OPERAB'
- CPEPABILITY 1.6 A syste",
subsystem,
- train, comiponent or device shall be OPERABLE or ha; e OPERAB! LITY when it is capable of performing its speci,ied function(s).
Implicit in this definition shall.
be the assumpiion that all necessary attendant instrumentation, controls, 'normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are reouired for th'e system, subsystem,
- train, component or device to per orm its function(s) are also capable of:*
per ormiing-their related support function(s).*
- 0 Auous i, 1 4, 1 981 and Auoust 1 7, 1 981 the fol 1 owi nc sa i e.y-rel c ted ca binets, motor coA i rol centers,.
and swi tchgea r were di s covered to have i ncdequate se i srili c support:
(a) 600V motor control centers, Unit' only numbers NiCC-2-AN-A and D,
(b) 4 KV Switchoear Busses/Cabinets numbers Tll A,B,C, and D for Unit 1
and T21 A,B,C, and D
os Unit 2, and (c) 600V Switchoear Buses/Cabinets numbers 11 A,B.C and D for Unit 1
and 21 A,B.C, and D for Unit 2.
The above equipment shall be declared operable providino the ollowino restrictions are me.:
C.
COOK -
UNIT 2 Amendment No; 35
'V Continued (1).";cactor oower shall be decreased until ei-.her
'.Dl reactor power is reached or temporary bracing of one train of equipment is completed.
(2) If the temporary bracing is not installed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> af.er reaching 60~
. power, urther.approval or operation must be obtained from the VRC Staff.'3)
The unit may be operated up to 100.-.'ower after temporary bracino is installeo on one train of equipment.
However, the second train must be properlv braceo 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 modi,ications to provide adequate seismic support for the equipment involved shall be completed by August 21, 1981.'.
C.
COOK - UNIT 2 1-1 a
/
Amendment No.
35
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-'atic isolation valve system, or
- b. Closed by manual valves, blind flanges, or deactivated auto-matic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
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.
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 2 1-2
I