ML19350E335
| ML19350E335 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/09/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350E336 | List: |
| References | |
| NUDOCS 8106170336 | |
| Download: ML19350E335 (10) | |
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UNITED STATES dE I%
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 O
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDi1ENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application by Nebraska Public Power District dated March 31, 1981 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 Commission; C.
There is reasonable assurance (1) that the activities authori::ed by this amendnent 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.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of its date of issuance, FOR THE NUCLEAR REGULATORY COMMISSION t
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Thomas
. Ippolito, Chief
_l Operati.ng Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Dated: June 9, 1981 D
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ATTACHMENT TO LICENSE Af1ErlDMENT N0. 71 6
FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO.'50-298-Remove the following pages of the Appendix A and B Technical Specifications and replace with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines 'indicati.ng the area of change,-
3 Remove Insert Appendix A Appendix A Ill iii iiia iiia Appendix B Appendix a 2
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TABLE OF CONTD1TS (Cont 'd.)
Page No.
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.14 Fire Detection System 4.14 216b 3.15 Fire Suppressien Water System 4.15 216b 3.16 Spray and/or Sprinkler System (Fire Protection) 4.16 216e 3.17 Carbon Dioxide System 4.17 216f 3.18 Fire Hose Stations 4.18 216g 3.19 Fire Barrier Penetration Fire Seals 4.19 216h 3.20. Yard Fire Hydrant and Hydratt Hose House 4.20 2161 l
MMOR DESIGN FEATURES 5.1 Site Features 217 5.2 Reactor 217 5.3 Reactor Vessel 217 5.4 Containment 217 5.5 Fuel Storage 218 5.&
Seismic Design 218 57 parge Traffic 218 ADMINISTRATIVE CONTROLS i
6.1 Organization 219 l
6.2 Review and Audit 220 6.2.1.A Station Operations Review Committee (SORC) 220 A.1 Membership 220 A.2 Meeting Frequency 220 A.3 Quorum 220 A.4 Responsibilities 220 A.5 Authority 221 A.6 Records 221 6.2.1.B NPPD Safety Review and Audit Board (SRAB) 222 l
B.1 Membership 223 I
B.2 Meeting Frequency 223 B.3 Quorum 223 B.4 Responsibilities 223 B.5 Authority 224 B.6 Records 225 B.7 Procedures 225 B.8 Fire Protection Inspection 225 i
111
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TAP,LE OF CONTENTS (Cont 'd. )
Page No.
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 6.3 Station Operating Procedures 226 6.3.1 (Introduction) 226 6.3.2 (Integrated and System Procedures) 226 6.3.3 (Maintenance and Test Procedures) 226 6.3.4 (Radiation Control Procedures) 226 6.3.5 (High Radiation Areas) 226a 6.3.6 (Implementation Review of Procedures) 226a 6.3.7 (Temporary Changes to Procedures) 226a 6.3.8 (Drills) 226a 6.4 Actions to be Taken in the Event of Occurrences Specified In Section 6.7.2.A 227 6.5 Actions to be Taken if a Safety Limit is Exceeded 227 6.6 Station Operating Recreds 228 6.6.1 (5 year retention) 228 6.6.2 (life retention) 228 6.6.3 (2 year retention) 229 6.7 Station Reporting Requirements 230 6.7.1 Routine Reports 230
.A (Introduction) 230
.B Startup Report 230
.C
' Annual Reports 230 e
.D Monthly Operating Report 231 6.7.2
!.eportable occurrences 231
.A Prompt Notification with Written Followup 232
.B Thirty Day Written Reports 234 6.7.3 Unique Reporting Requiremencs 235 6,8 Environmental Qualification 235a 6.9 System' Integrity Monitoring Program 235a 6,10 Iodine Monitoring Program 235a l
Anendment No. 71 iiia
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2.0 EINIRO11MEllTAL PROTECTIOli C0tIDITIO'i 3.0 tidi1LTOR111C I!EQUIRDIEllT s
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4 3.1.4 Maximum Stu/hr.
2.1.4 Maximum Btu /hr.
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110t applicable.
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l 2.1.7 Deicing Operations 3.1.7 Deicing Operatioim flat applicable, llot applicable.
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110t Applicable. See Section 4.1.1.b.
14ot applicable. See Section 4.1.1.b.
2.2.2 Discharge Velocity 3.2.2 Discharge Velocity tiot applicable.
tiot applicable.
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t 2.2.3 Size of ttixing Zone 3.2.3 Size of 111xing Zone l
Ilot applicable.
flot applicable.
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}laximum and flinicaum Flow Restrictions 3.2.4 tiaximans and ttinisauis Flow Restrictions l
Not applicable, tiot applicable.
2.2.5 Reservoir Drawdown 3.2.5 Reservoir Drawdown n.
I Ilot applicable.
Ilot applicable.
2.2.6 Erosion 3.2.6 Erosion tiot applicable.
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6.4./.G (Qant'd) un. ige evalu.it ion ;.c r the
. Lu i l e r inni Pi e:,:,u s e W
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for tin-condi t ions sitt ini a in t..
de. i;;n r;pecitienton.
The loca t i on:; to be monitored :: hall iw :
a.
Th'e feed wa ter nozzles b.
Tne shell at or near the waterline c.
The flange studs 2.
!!onitoring, Recording, Evaluating, and lieporting a.
Operational tratisients tnat occur during plant operations will, at least annually, be reviewed and conpared to the transient conditions defined in the component stress report for the locations listed in 1 above, and used as a basis for the existing fatigue analysis.
b.
The nuaber of transients which are comparable to or more severe than the transient evaluated in the stress report Code fatigue usage calculations will be recorded in an operating log book.
For those transients which are more severe, available data, such as the metal and fluid temperatures, pressures, flow rates, and other conditions will be recorded in the log book.
c.
The number of transient events that exceed the design specification quantity diid the number of transient events with a severity greater
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than that included in the existing Code fatigue usage calculations shall be added. When this suu exceeds the predicated nunber of 2
design condition events by twenty-five, a fatigue usage evaluation of such events will be performed for the af fected portion of the RCPB.
L it.
Records of individual plant staf f members showing qualifications, training and retraining.
I.
Records for Environmental Qualification wnich are covered under the provisions of paragraph O.8.
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6.6.3 Records and lods relating to the following iteus shall be kept for two l
years.
l A.
The test results, in units of microcuries, for le ak tests of sources performed pursuant to Specification 3.8. A.
B.
Records of annual physical inventories verifying accountability of the sources on record.
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I 1.
See paragraph !!-415.2, ASIC Section III, 1965 Edition.
2.
The Code rules permit exclusion of twenty-five (25) stress cycles from secondary l
stress and fatigue usage evaluation.
(See paragraphs II-412(t)(3) and ll-417.10(f) of the Sunuer 1968 Addenda to AS!!E Section III, 1968 Edition.)
Amendment No. 71
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