ML17331A016
| ML17331A016 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/14/1993 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A017 | List: |
| References | |
| NUDOCS 9302160158 | |
| Download: ML17331A016 (9) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 MENDMENT TO FACILITY OPERATING IC NS Amendment No. 169 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated July 26, 1991 as supplemented June 7,
- 1991, February 4, April 1, and October 26,
- 1992, 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; 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 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.
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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
- 169, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9302160158 930114 PDR ADCICK 05000315 P
PDR,j
3.
Further, the license is amended, by changes to paragraph 2.C.(5) and adding paragraph 2.C.(8) to read as follows:*
(5)
S ent Fuel Pool Stora e
The licensee is authorized to store D. C. Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated, up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.
Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95X Uranium-235.
(8)
The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.
Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612, "Controls of Heavy Loads at Nuclear Power Plants."
Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.
4.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION pV~~
Ledyard B. Harsh, Director Project Directorate III-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Attachments:
1.
Changes to the Technical Specifications 2.
Page 4 and 4a replaces 3a and 4 of License*
Date of Issuance:
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- Page 4 and 4a is attached, for convenience, for the composite license to reflect the change.
~'
ent Fuel Pool Stora e CO CO Ch The licensee is authorized to store D. C. Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated, up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.
Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95K Uranium-235.
Amendment No. 32, 10-16-79 Deleted - Amendment No. 80, 04-27-84 Secondar Water Chemistr Monitorin Pro ram CO Ch O
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The licensee shall inplement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall be described in the station chemistry manual and shall include:
l.
Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of data; 5.
Procedures defining corrective actions for off control point chemistry conditions; and 6.
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective actions."
The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the, pool for the duration of the spent fuel pool reracking project.
Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-
- 0612, "Controls of Heavy Loads at Nuclear Power Plants."
Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.
tD CO Ch CU CU O
Ch O
E
- 4a-2.D.
Ph sical Protectio The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Donald C.
Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988; "Donald C.
Cook Nuclear Plant Training and gualification Plan," with revisions submitted through December 19, 1986; and "Donald C.
Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.
Changes made in accordance with 10 CFR )3.55 shall be implemented in accordance with the schedule set forth therein.
TTACHMENT TO ICENSE AMENDMENT NO. 169 TO FACILIT OPERATING LICENSE NO.
PR-58 l!0 TET E
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
- QEMOllD, 3/4 9-3 3/4 9-19 5-4 5-5 5-6 5-7 5-8 5-9
~INSER 3/4 9-3 3/4 9-19 5-4 5-5 5-6 5-7 5-7a 5-7b 5-8 5-9
REFUELING OPERATIONS DECAY TIME 4
LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
Pith the reactor subcritical for less than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel.
The provisions of Specification 3.0.3 are not applicable, SURVEILLANCE REOUIRENENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> by verification of the date anc time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.
COOK NUCLEAR PLANT - UNIT 1 3/4 9-3 AMENDMENT NO.
169
REFUELING OPERATIONS STORAGE POOL BORON CONCENTRATION*
LIMITING CONDITION FOR OPERATION 3.9.15 A boron concentration of greater than or equal to 2,400 ppm shall be maintained in the fuel storage pool.
APPLICABILITY: At all times.
ACTION:
Vith the requirements of the specification not satisfied, suspend all movement of fuel assemblies in the fuel storage pool and restore the boron concentration to within its limit prior to resuming fuel movement.
The provisions of Specification 3.0.3 are not applicable.
SURVEIL~~PCE RE UIR~ fENTS 4.9.15 The boron concentration in the fuel storage pool shall be determined to be at least at its minimum required at least once per 7 days.
- Shared system with Cook Nuclear Plant
- Unit 2 COOK NUCLEAR PLANT - UNIT 1 3/4 9-19 AMENDMENT NO. )Pg, 169
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DESIGN FEATURES DESIGN PRESSURE AND T""OPERATE'RE 5.2.2 The reactor containment building is designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.
P E'i~TRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 5.4 of the FSAR with allowance for normal degradation pursuan" to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASS~'fBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy-4.
Each fuel rod sha' have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235
'eload fuel shall be similar in physical design to the initial core loading and shall have a
maximum nominal enrichment of 4. 95 weight percent U-235.
s CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5
percent cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TE.gPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
COOK NUCLEAR PLANT - UNIT 1 5-4 mENDXENT NO. EP2
DESIGN FEATURES a.
In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
c ~
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is o
680 F.
VOLUNE 5.4.2 5.5 The total contained volume of the reactor coolant system is 12,612
+ 100 cubic feet at a nominal T of 70 F.
avg EMERGENCY CORE COOLING SYSTEMS 5'.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY -
SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
A k ff equivalent to less than 0.95 when flooded with eff unborated water, b.
A nominal 8.97 inch center-to-center distance between fuel assemblies placed in the storage racks.
c
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The fuel assemblies will be classified as acceptable for Region 1, Region 2, or Region 3 storage based upon
" ir assembly average burnup versus initial nominal enrichment.
Cells acceptable for Region 1, Region 2, and Region 3 assembly storage are indicated in Figures 5.6-1 and 5.6-2.
Assemblies that are acceptable for storage in Region 1, Region 2, and Region 3 must meet the design criteria that define the regions as follows; COOK NUCLEAR PLANT - UNIT 1 5-5 AMENDMENT NO.
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169