ML20037B441
| ML20037B441 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-19-A-035, DPR-19-A-35) |
| Issue date: | 03/01/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037B438 | List: |
| References | |
| NUDOCS 8009260724 | |
| Download: ML20037B441 (7) | |
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,d"pa tic rw oSe UNITED STATES O'
NUCLEAR REGULATORY COMMisslON k
g WASHINGTON D. C. 20555
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c 49....,C C0!I"0NWEALTH EDIS0N C0!PANY DOCKET NO. 50-237 DRESDEN N'JCLEAR POWER STATION UNIT NO. 2 AMENDitENT TO PROVISIONAL OPERATING LICENSE Amendment No. 35 License No. DPR-19 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 ir 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 4
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Conmission's regulations and all applicable requirements have been satisfied.
8009260 M y
. 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-19 is hereby amended to read as-follows:
B.
Technical Specifications The Technical Specifications contair.?d in Appendix A, as' revised through Amendment No. a5, 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 RIGULATORY. COMMISSION k,
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/s z2, s,.. 's Dennis L. Ziemann, hief Operating Reactors Branch 72 Division of Operating Reactors
Attachment:
a Changes to the Technical Specifications Date of Issuance: March 1,1978
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' ATTACHMENT TO LICENSE AMENDMENT NO. 35 P?O'l'ISIONAL OPERATING LICENSE NO. DPR-19 s
k DOCKET NO. 50-237 x
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s F.eplace the fc.1197ing existing pages of the Technical Specifications s'
with the attached revised pages. Changed areas on the revised pages
~ ire shewn by a barginal line-.
Insert Pages Re cve Pages __
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171 'is Delete 172 N
Delete 173 Del ete i
174 Delete 177 177 177a Del ete 177b 177b s
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.f c.? plant. Operating Procedures 11. Tests and experiments.
Detailed written procedures including A.
. Procedure to ensure safe shutdown of the,
applicable checkof f lists covering items 9.
1 lated below shall be prepared, approved, pl a nt.,
and cdhered to:
- 10. Station Security Plan and impicmenting Hannal startup, operation, an'd shutdown '
procedures..
1.
of the reactor 1and other systems and ccmponents involving nuclear safety ot~ 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 forescen 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 leaks, organized to meet the-requirements of 10 CFR 20.
I and abnormal reactivity changes.
Proceduras for itcms identified in Specifica-Emergency conditions involving potential' C.
1.
tion 6.2.A cnd any chances to such proceduras 4.
or actual release of radioactivity -
shall be reviewcd and appros/ad by the Opsricing
" Generating 5tations Emergency Plan" Engineer and the Technical Staff Supervisor and station emergency and abnormal in the areas of operation, fuel handling, or procedures.
instrcment raintentnce, ar.d by Mainter.cnce S.
Instrumentation operation which could Engineer and Technical Staff Sur.ervisor in the have an ef fect on; the safety of the areas of plant maintenance E.nd clant inspec-Procedures fcr iter.u idef.tified in I
tion.
facility-Speci ficatien 5.2.B tr.d any changcs. to such p ocad'a as si'. ll be revic.:cd and anproved L.y 6
Preven'tive and corrective maintenance the T chnical Staf f Scparvisor and ae '<a:'ip.
operations which could have an effect on the safety of the facility, lo icti Chartical Sc;0cvitor. At leLst cne parsca approving cr.ch of tha cove 7.
Surveillance and testing-requirements.
penccdures shall hold a va s:d sar.1or operator,s license.
In addition, these procadures and changes thereto nust hcVe authorizatica by the Statice Superintend:nt before being icplemented, t.nen.jirent No.J[ 35
2.
'dork and instruction type procedures which 1.-.?l e :'en t ap; rov:a. maintenance or :rac..,1 cation li.
crecedures shall be a;'yeaved and authcrized
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Te 'taintencacc/P.cdific:ticn Pracedure" utilized for safety reictad vor'<
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i requirezcats of ";.2. ' er 6.2.0 :. cay 'bc apprcycd bv the DaI,artment Hacds.
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'.. The intent of the original precedure is not altered.
2.
The chance is.~oproved b.v. two terb.crs s
c" t:-^ plcnt car.r;sent staff, at '!ccst one of whcn hoid, c Scnice Reactor
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Tha change is documentad, revic :cd by the Or;ite Ravicw cad :r.ecc.tigative Function r. apprcycd by the 5tsion Superintendent v i l '. i n 1., c.a.vs 0; 1rc.> t ccen ta ti c n.
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ir !ii'. of the crergency precedures described Speci ficction 6.2. A.? thall be conducted p1 t.--.^d
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169 (next page is 175) n
. No. If., 35
( 6 RFrenTitlG REQUIREMENTS in addition to the applicable reporting requirements of Title 10 Code of Federal Regulations,l following identified reports shall be submitted to the Director of the appropriate Regiona the of rice of inspection and Enforcement unless otherwise noted.
A.
Ibutine_ Reports 1.
Startop Report A summary report of plant startup and power escalation testing shall be submitted fallowing (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) Installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (h) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each 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 comnitmen'ts shall be included in this report.
Startup reports shall be submitted within (I) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months 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, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three nonths until all three events have been completed.
177 Amendment No. 35 (next page is 177h
1 2.
A tabulation shall be submitted on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their assocInted man ran exposure according to work and job functions, 1/e.g., reactor operations l
and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions i
may be estimates based on pocket dosimeter TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted fce, in the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
3 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a Onthly basis to the Director, Office of Management Information and Program Control, US Huelear Regu-latory Cotuission, Washington, DC 20555, with a copy to the appropriate Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.
I 3.
Reportable Occurrences Reportable occurrences, including corrective actions and i es to prevent reoccurrence, shall be reported to the NRC.
In general, the importance of an occur.
ice with respect to safety significance determines the immediacy of reporting required.
In some case however, the significance of an event may not be obvious at the time of its occurrence.
In such cases, the NRC shall be Informed promptly of an increased significance in the licensee's assessment of the event.
In addition, supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to t:::
original report date.
If This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
9 9
177h A mndment flo. 35
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