ML20037B439
| ML20037B439 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-02-A-024, DPR-2-A-24) |
| Issue date: | 03/01/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037B438 | List: |
| References | |
| NUDOCS 8009260722 | |
| Download: ML20037B439 (7) | |
Text
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NUCLEAR REGULATORY COMMisslON
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-10 DRESDEN NUOLEAR POWER' STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
l Amendment No. 24 License No. DPR-2 1.
The Nuclear Regulatory Commission (the Commission) 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 amended (the Act), and the Commission's rules and regulations set forth.n 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 conmon 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 Comission's regulations and all applicable requirements have been satisfied.
.8009eso 7 M
. 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 License No. DPR-2 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L,
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k Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date _of Issuance: March 1,1978
+
ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. DPR-2 DOCKET NO. 50-10
- 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
-131 131 132 132 133 Delete 134 Delete 135 Delete 136 Delete 137 Delete 142 142 142a Delete 142b 142b d
1 4
I L
6.2 pl M Op,aLing procedures 8.
Tests and experiments.
Detailed written procedures including A.
procedure to ensure safe shutdown of the applicable checkof f lists covering items 9.
- 1isted belcw sha'll be prepared, approved, plant.
and adhered to:
Station Security Plan and implementing 10.
Formal startup. operation, and shutdown procedures..
1.
of the reactor and nther systems and components 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 Actions to be taken to correct specific permissible radiation exposure and shall be 3
and foreseen potential malfunctions of consistent with the requirements of 10 CFR This radiation protection program shall_be systems or components including responses 20.
to alarms, suspected primary system lcaks, orgarrized to meet the requirements of 10 CFR ?..
and abnormal reactivity changes.
C.
1.
Procedures for items identified in Specifica-Emergency conditions involving potential' tion 6.2.A and any changes to such procedures 4.
or actual release of radioactivity -
shall be reviewed and approved by the Operating
Generating Stations Emergency Plan" Engineer and the Technical Staff Supervisor and station emergency and abnormal in the areas of operation,' feel handling, or procedures, instrument maintenance, and by Maintenance Engineer and Technical Staff Supervisor in the 5.
Instrumentation operation which could areas of plant maintenance and plant inspec-have an effect on.the safety of the tion.
procedures for items identified in.
Speci fication 6.2.B and any changes to such facili ty.
procedures shall be reviewed and cpproved by 6
Preventive and corrective maintenance the l'echnical Staf f Separvisor and the Radic-operations which could have an effect logical Cheaical Supervisor.
At least on the safety of the facility.
one person approving cach of the above proceduces shall hold a valid senior operatar :>-
7.
Surveillance ~and testing requirements.
license.
In addition, these procedures and changes thereto must hcVe authorization by the Station Superintende.t bafore being in.plemented.
1.31 P:. M ::at No. y, 24
2.
Work and instruction type procedures which ir.olement appraved mainten:,nce er cadification prccedures shall be approved cnd cuthorized by the P.aintenance Engineer 5:here the written authority has been provided by the Station Superintendent.
The " Maintenance /f'odification Procedure" utilized for safety related work shall be so approved only if procedures referenced in the ".ainte".ance/N;dificction Procedure" have been approved as required by 6.2. A.
Procedures v.hich do not fall within the requircments of 6.2.A or 6.2.B may be approved by the Ocpartment Heads.
O.
Tcmporary changcs to procedures 6.2.A and 6.2.0 above may be made provided:
s i.
The intent of the original procedure is not altered.
2.
The change is cporoved by t<:0 members of the plant n:anagamant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
3.
The change is documented, revie.:d by the Onsite haview and Investigative Function and apprcved by tile Stetien Superintendnat within 14 days of implemantation.
E.
Drilli af the emercc.:cy proccdures dcccribed in S.:.-ifici..ica C.:./.4 shall bs condectcd cucrtcely.
Tnase drilis will be planned so that during the course of the year, ccmunica-tion links are tested cnd outside agencies
- re contacted.
132 (next page is 138)
Amenenent No. 24
s
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6.6 MEp0RTIllG REQllIRDIENTS In addit ion to the applicabic reporting requirements of Title'10, Code of Federal Regulations, following identified reports shall be submitted to the Director of the appropriate Regional the office of inspection and Enforcement unicss otherwise noted.
A.
Routine Reports 1.
Startup Report A sunmary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned lucrease in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfornance of the plant, The report shall address cach of the tests. identified in the FSAR and shall in general include 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 commitments shall be included in this report.
Startup reports shall be submit ted within (1) 90 days following' completion of the startup test (2) 90 days following resumption or conmencement of commercial power operation, or
- prodram, (3) 9 months following initial criticality, whichever is carliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or conmencement of commercial power operation), supplementary reports shall be every three nonths until all three events have been completed.
submitted at least 142 (next page is 142b)
An"mimen t No. 24
A tab 61ation sha11 be 'submitt6d ~on ah' adhUal'liddis~oT the16umlier' of ~ station, utility and f
~
receiving exposures greator than 100 mrem /yr and 2
other personnel (including contractors) l their associated man rem exposure according to work and job functions lje.g., reactor operations routine maintenance, special maintenance (describe and surveillance, inservice inspection, The dose assignment to various duty functions maintenance), waste processing, and refueling.
Small exposures may be estimates based on pocket dosimeter, TLD, or film badge measurements.
In the totalling less than 20% of the individual total dose need not be accounted for.1 cast aggregate, at be assigned to specific major work functions.
3.
Monthly Operating Iteport Routine reports of operating statistics and snutdown experience shall be submitted on a monthly basis to the Director, Office of Ibnagernent Information and Program Control, US Nuclear Regu-20S55, with a copy to the appropriate Regional Office, to DC latory Cc:r.::iunion, Wnshinst, ton,
each month following the calendar month covered by the report.
arrive no later than the-15th of T., Reportable Occurrencen including correct.1ve actions and measures to prevent reoccurrence, shall be to safety significance Reportabic occurrences, In general,-the importance of an occ'urrence with respectIn some cases, however, the significan reported to t'ic NRC.
determines the immediacy of reporting required.
In such cases, the NRC shall be informed promptly may not be Cavious at the time of its occurrence.
In addition, supplemental of an increased significance in the licensce's assessment of the event.
In case of corrected or fully describe final resolution of occurrence.
report shall be completed and reference shall be made to the reports may be required to supplemental reports, a licensee event original report date.
20.
tabulation supplements the requirements of 20.407 of 10 CFR Part 1/ This 142b