ML19323C780
| ML19323C780 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/10/1978 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323C736 | List: |
| References | |
| FOIA-80-162 NUDOCS 8005190177 | |
| Download: ML19323C780 (6) | |
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~ !ls~. i C_0:15UIiERS PO!1ER COMPA!j,Y, DOCKET !!0. 50-155 BIG P,0CK P0 lilt i:UCLEi.d P!.AflT AllEllDMEf!T TO OPERATIffG LICEllSE, Amendment f;o. 15 License fio. DPP-6 1.
The fluclear Regulatory Conmission (the Conmission) has found that:
A.
The applications for amendment by Consumer Power Company (the licensee) dated l'ay 17 and !!over.:ber 11, 1977, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission'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 Conmission; C.
There is reasonable assurance (1) 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 Ccsmission's regulations; D.
The issuance of this amendment will not be inimical to the conmen defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part
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51 of the Comnission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is a:.. ended by changes tc thr Technical Specifications as indicated in the attachmcnt to this lictnre anendment and paragraph 2.C(2) of facility License !!o. EPR-6 is hereby a, tended to read as follows:
(2),lechnical Spe,cificatigis The Technical Specifications contained in I,ppendix A. c.s revised through Ar.endment ilo.16, are hereby incorporat d in the license.
The licensee shcIl operate the facility in accordance with the Technical Spccifications.
3.
This license'amendn.ent is ef fective as of the Gte of its issuance.
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FOR THE liUCLEAR REGULATOP.Y C0:'lilSS10 :
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Don K. Davis, Acting C!ief Operating Reactorr. F. ranch F2 l
Division cf Operating bactors.
Attach::;ent:
Changes to the Technical Specifications Date of Issuance: January 10, 1978 1
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1 ATTACHMEf1T TO LICEtiSE AMEtiDMErlT tl0.16 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 1.
Replace pages 10-1,10-1.5 and 10-22 of the Technical Specifications contained in Appendix A of License No. DPR-6 with the attached pages 10-1, 10-13 and 10-22. The changed area of the revised pagesis reflected by a marginal line.
2.
Delete page 10-14 in its entirety.
3.
Delete pages 10-23 through 10-27 entirely.
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6.0 ALMDISB1ATIVE CONTROLS (NOTE: This is the new format of the Tecl.nical S; ecifications to be inud
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entirely in the near-future. This secticn replaces the fellowing 6.1 RESPONSIBILITY sections of the current Technical Specifications; 7.1, 7.1,.1-7.1.'0, 7.2, 7.2.1-7.2.3, 7.5, 7.5.1-7,5.6, and 7.7 entirely) 6.1.1 The Plant Superir.tendent shall be responsible for overall plant cperation and shall delegate in writing the~ succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for plans management and technical support shall be as shown on Figure 6.2-1.
O PLANT STAFF 6.2.2 The plant orge.nization shall be as chovn on Figure 6.2-2 and:
Each on-duty shifs shall be composed of at least the minimum shift crew compqsition chovn a.
in Table 6.2-1.
b.
At leact one licensed Operator chall be in the contiol room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor.startup (to a power level >5 percent), scheduled reactor shutdown and during recovery fro':: reactor
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An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
All core alterations after the initial fuel loadin2 shall either be perforned by a licensed e.
Operator under the supervision of a licensed Senior Operator or a non-licensed Operator directly supervised by a licensed Senior Operator (or a licensed Senior Operator Limited to Fuel Handling) who has no other concurrent responsibilities during this operation.
6.3 PLANT STAFF QUALIFICATIONS 6.3.1 Each usaber of the plant staff shc11 ccet or exceed the minimum qualifications of ANSI N18.1-1971 for coapar..ble positions.
6.3.2 Either the llcalth Physicist or the Chemistry and Hadiut,lon Protect,lun Uupervisor shall meet or exceed the quallricat. ions of Regulatory Guide 1.8, Gopte,:.cr 1975 10-1 Amend-n: :... o, J r,
6,9.1 (contd) b.
Annual Report.
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of 10 CFR 20.407 should be submitted, prior to March 1 of each year.n annual This annual report s' hall include:
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A tabulation on an annual basis of the number of station, utility and other personnel (incl di contractors) receiving exposures greater than 100 milem/y.r and their usnoeinted man-ilem exposure u ng according to work and job functions, eg, reactor operations and surveillance, inservice inspecti routine maintenance, special maintenance (describe maintenance), vaste processing, and refu on, The dose assignment to various duty functions may be estimates based on pocket dosimeter film badge measurements.
Small' exposures totaling less than 20% of the individual total dose need (3
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not be accounted for.
external sources shall be assigned to specific major work functions.In the aggregate, at leas c.
Monthly Operating Report basis to. the Director, Office of Management Information and Program latory Commission, Washington, DC arrive no later than the 15th of 20555, with a copy to the appropriate Regional office, to each month fbiloving the calendar month covered by the report.
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10-13 Amendment Nii. 9,16
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Records of inservice inspectionq perforped pursuant to these Technical Specifications.
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h.
Records of Quality Assurance activitia s required by the QA Manual to be retained for the duration of the facility operating license.
1.
Records of reviews perfonned for changes made to procedures or equip =ent or reviews of tests and experiments pursuant to 10 CFR 50 59
(.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements b
of 10 CFR, Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
ii.12 DELETED e
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10-22
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