ML20024E513
| ML20024E513 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/11/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20024E511 | List: |
| References | |
| NUDOCS 8308150201 | |
| Download: ML20024E513 (5) | |
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UNITED STATES 7
l' "' ( i S NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 gy/
h CONSUMERS POWER'. COMPANY,
,j, DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated May 27, 1983, 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 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 eadangering the health and safety of the public; and (ii) that such activities will be conducted in compli-ance 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 Comission's regulations and all j
applicable requirements have been satisfied.
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b P308150201 830811 PDR ADDCK 05000155 P
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Accordingly, the license is amended by changes to the Technical
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Specifications as indicated in the attachment to this license l
amenenent and~ Paragraph 2.'C(2) of Fac~ility Operating-t.icense- - -- -
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No. DPR-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 60, are hereby incorporated in the. license. The licensee shall operate the facilit'y in accordance with the lechnical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
i Dennis M. Crutchfiel, Chief 4
i Operating Reactors B anch #5 Division of Licensing-
Attachment:
Changes to the Technical Specifications Date of Issuance: August 11, 1983
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ATTACHMENT TO LICENSE AMENDMENT N0. 60 FACILITY OPERATING LICENSE N0. DPR,6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages include the captioned amendment number and marginal lines indicating the area of change.
PAGES 5-8 7-3b t
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5.1.6 Seur:es Type A::1===y Beryllium Up to Two Initial Sources Quanti:7 Up to Four Auxiliary Sources o
Neutron sou-cen my ha envinaa to assure neutren visihility is sufficient te satis ^/ the require:ents of Sectic: 7.3.2(d).
If neutre:
se=ces a e used te assist i_: providing this visibility, locatien of these sorces sb1' be as follows:
Lo caties The initial neut :: s==ces shall be placed in core positicas 02-59 and 09-52 a.s sh=ce. in Figue 3.1.
Up to feur auxiliary centre: sources =ty. be ec.:ained within fuel bu= dies 1: rod locaricas==== ally occupied by fuel rods or iner: rods.
Thesitzi Oes crittie:
The initici :e:::: s =ces shall.ccasis: cf a steel-jacketed anti===y pi=,1-1:2 diameter by 12 i=ches Ic:g, cestrally located en the vertical axis cf a st' eel-jacketed (Type 30!. SS) berylliu= cylinder 5-1/2 CD by 16 inches Ic g.
The as ire asse=bly, including supper:
strue:ure, is a cy11= der 79-7/16 inches ic g by 6-inches diameter which rests en a special orifice in a standard supper:-tube-and-cha= e1 a.s s e:bly. A lifting bail shall be provided fe handling y= poses. The assembly design shall allow adeqcate cooling aleng the s= face of the seu::e pi: a=d the cc:e: surface of the ass==bly.
The auxiliary :::::== se= des shel ea'ch c==sist of a hocogn=esods 50-50 ud::ure of asti===y-beryllium firs:==capsulated in a steel tube (Type 30!.:. SS), ther se ::darily==capsulated in a zirc==iu= alloy tube.
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o-8 Chance No. yf /
Amendment No,'g 60
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- eics :=: rate re er sha'.1 indi:ste a cini = cf :.. ee ::=:s
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a::::plished by withi aving the sta t-up cht:ber to e. regie: cf lover f1= and observing the reductic: inec=: rate.
In the event that neutron sc=ce strength is insufficient to produce the r,equired',co=t rate, an. approach to ekitice.lity j
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- for r'eacter start:.up shall be e.ilovei VfoVided 'that' the i
following ccaditic s are ret: -
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scr:e strength ceniitics, a critice.1 appree.ch(es } vith the ree.::cr vessel head-eff shall be perferred to eve.luate the cut-of-vessel lov-level dete::cr response and the ec :rel i
red withdraval seque
- e. ' Two additicca.1 lev-level det'e:-
ters shall be temporarily inserted i: the vessel to =c iter this head-off critical r.pproach(es).
T ese additione.1 detectors s%1' iniitate a ' '-- cf 3 cc=ts per se:cmd with e. sig=e.1-to-:cise re.tio of 3 to 1.
(ii)
Eve.luatics of instr =ent respenses dring the head-eff
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the estimated k,, cf the core reaches 0.cc5, ee.ch icv-e level cut-of-ecr..e sta-t-up detecter is reading e.. lee.st 3 eps vith a 3 *o 1 signe.1-to-noise ratio.
(iii) Critice.1 approaches vith the head c: and without the te:-
perary in-vessel icv-level detecters in se vice she.11 be permitted provided ths.: the instr =ent response require-
=ents of (ii) above he.ve been de:::stre.ted and provided that these se.=e requirements are also net dr ineach s
critice.1 approach with the head on.
Ner:a'. sta-.-up =ay ec tinue.r.:y time start-up count rate is e.: leas: 3 cc=:s per secc d vitS~s. -'-3 ~.: signe.1-to-noise ratio of 3.c 1.
(iv)
T e procedure of (1) and (ii) above shall be repeated by conductirs an additional head-eff critical approach (es) i in i.he event of either a core configr atic che.::ge er a significant charge in that part of the control rod vith-i dre. val seque::e for which the =1:i== count rate and signal-to-scise ratic specified above are not attainable.
4 (v)
The site reactor engineer or his alternate vill be c site du-ing e.11 head-cff critice.1 appr: aches and instrumen-l resp::se evaluaticas and dr ing the initial hee.d-c s:sr:-
up folleving head-off eye.lue. icss.
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Change No. /
Amendment No;
, 60
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