ML20037B442
| ML20037B442 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/01/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037B438 | List: |
| References | |
| NUDOCS 8009260725 | |
| Download: ML20037B442 (7) | |
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s,, g NUCLEAR REGULATORY COMMisslON l
WASHINGTON. D. C. 20555
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C0f!MONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION UNIT NO. 3 AMENDf;ENT TO FACILITY OPERATING LICENSE Amendment No. 32 i
License No. DPR j 1.
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated December 6,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (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 endancering the health and safety of the public, and (ii) that such activities
,l will be conducted in comoliance with the Conmission's regulations; f
D.
The issuance of this amendment will not be inimical to the comr.on defense and security or to the health and safety of 1
the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Concission's regulations and all applicable requirenents 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 3.B of Facility License No. DPR-25 is hereby amended to read as follows:
B.
Technical - Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, are hereby incorpo,ated in the license. The licensee shall operate the facility in accordance with the fechnical Specifications.
3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMl11SSION
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t... },. -b.. s... s DennisL.Ziemann/ Chief Operating Reactors Branch p2 Division of Operating Reactors
Attachment:
Changes to the Technical l
Specifications l
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Date of Issuance: March 1,1978 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Replace the following existing pages' of the Technical Specifications with the attached revised pages. Changed areas on the revised pages are shown by a marginal line.
Remove Pages Insert Pages 168 168 169 169 170 Delete 171 Delete 172 Delete 173 Del ete 174 Delete 177 177 177a Del ete 177b 177b
G.2, Plant.0perating Proccilurcs 8.
Tests and experiments, Detailed written procedures including A.
applicable checkoff.1ists covering items 9.
Procedure to ensure safe shutdown of the,
listed below shall be prepared, approved, and cdhered to:
plant.
- 10. Station Security Plan and implementing Itormal startup, operation, and shutdown procedures..
1.
of the reactor'and other systems and ccmponents involving nuclear safety of the facility.
B. ' Radiation control procedures shall be main-2.
Refueling operations.
tained, made available to all station personnel and adhered to. These procedures shall show 3.
Actions to be: taken to correct specific permissible radiation exposure and shall be and forescen potential malfunctions of consistent with the requirements of 10 CFR systems or components including responses This radiation protection program shall be 20.
to alarms, suspected primary sys te:m leaks, organized to meet the requirements of 10 CFR 20.
and abnormal reactivity changes.
Proceduras for ittras id'entified in Specifica-Emergency conditions involving potential' C.
1, tica 6.2.A and any changes to such precedures'
- 4. i or actual release of radioactivity -
shall be revic~rmd End 2% roved by the Gparating
," Generating Stations Emergency Plan" Enginear and the Tcchnichl Staff Supervisor and station emergency and abnormal in the areas of operation, fuel Str.dling, or procedures.
instre:aant maintentaca, ar.d bv Mainten:nce 5'.
Instrumentatjon operation which'could Encincer and Techaical Staff Sucervisor in the have an ef fe6L on. the safety of the areas of plant maintenance and clant inspec-tion.
Procedurcs fcr itams idcr.tifiad in facility.
Spaci ficatien 6.2.3 and any char."cs to such procad ras shall be revicscd an[ anproved by 6,
Preventive ar.d corrective maintenance operations which could have an effect the Tachnical Staf f Separvisor and d.e Radin.
least on the safet.y of the facility.
logicc:. Chacical Sparvisar.
- c. c cne pafsca approving aach of the a ovep 7
Surveillance and testing requirements.
liccnse.
In addition, these procaduras and changes tharcto must hcvc authoriaatica by the Station Superintand:r.t before beir.g impliccated.
168 T. r r:+mn t No. M. 32
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6.6 REPORTitlG REQUIREMENTS 4
In addition to the appIlcable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Of fice of Inspection and Enforcement unless otherwise noted.
A.
Routine Reports 1.
Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license invo;.Ing a planned increase in power level. (3) Installation of fuel that has a different design or has been manufactured by a dif ferent fuel supplier, and (f ) modifications that may have significantly altered the t
nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general loclude a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitmen'ts shall be included in this report.
Startup reports shall be submitted within (1) 90 days foilowing completion of the startup test program, (2) 90 days following resumption or conv ncement of commercial power operation, or (3) 9 nonths following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, i
and resumption or commencement of commercial power operation), supplementary reports shall be submitted at Icast every three months until all three events have been completed.
177 Amendment flo. 32 (next page is 177b
j A tabulation r.hcll ta submitted en on annual basis or the number of station, utility end other personnel 2.
(!ncluding centracters) receiving exposures greater than 100 mrem /yr and their cssociated r.. n ren expecut e according to work and job functions,1/c.g., reactor cperations l
and surveillance, incervice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refuelin:;. The dose assignment to various duty functions Small exposures may be estimates b. sed on pocket dosimeter,1LD, or film badge measurements.
totalling less than 20% of the Individual total dose need not be.ccounted for.
In the least 80% of the total whole body dose received from external sources shall aggregate, at be assigned to specific major work functions.
3 Monthlv Operating Report
.i Routine reports of operating statistics and snutdown experience shall be submitted on a monthly basis to the Director, Office of Management Inrcerotion and Program Centrol, US Nuclear Regt-f' latory Comuission, Washington, DC 20555, with a copy to the appropriate Regional Office, to t'-
arriva no later than the 15th of each month following the calendar month covered by.the report.
B.
PgcortAbic Occurrences including corrective actions and measures to prevent reoccurrence, shall be Reportable occurrences, reported to the MRC.
In general, the importance of an occurrence *<ith respect to safety significance determines the immediacy of reporting required.
In som.c cases, hosever, the significance of an event may not be cbvious at the ticia of its occurrence.
In such cases. the NRC shall be inforced promptly of an increased significance in the licensec's assessment of the avent, in addition, supple.T. ental In case of corrected or reports may be r.: quired to fully describe fir.at resolution cf occurrence.
supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
!/ lhis tabulation supplements the rcquirements of 20.407 of 10 CFR Part 20.
4 e
177b ww w 2