ML20031E155
| ML20031E155 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/22/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031E152 | List: |
| References | |
| NUDOCS 8110150154 | |
| Download: ML20031E155 (5) | |
Text
.
,,(puauq\\.,
UNITED STATES NUCLEAR REGULATORY COMMISSION y'
W<
g WAsMNGTON. O. C. 206gul j
\\... /
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-40
'. The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The applichtica for ame1dment by the Omaha Public Power District (the licensee) dated March 2i, 1981, as sunolemented August 3,1981 complies with the standards and requirements of the A*,nmic 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 appli-cation, the provisions of the Act, and th'e r61es and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conduct d 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
(
l l
0110150154 910922 PM ADOCK 05000295 P
pg
=
2 2.
Accordingly, Facility Operating License do. OPR-40 is amended by changes to the Technical Specifications as indicated in the attacament to this license amendment, and paragraph 3.B. of Facility Operating License No. OPR-40 is hereby amended to
' read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, 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
(& '
Rcbert A. Clark, Chief Operating,Rgactors Branch #3 Civision of L~ifensing Attachrent:
Changes to the Technical Speci fications Date of Issuance: Septepber 22, 1981 E
e D
W
<w
-t-
.g-,
-,,-.m--m-T
-p,a ee yq-y-
y---.-,-w--
ye em y
y
,g,,_
--m-c --- ---
r p-.--
a ATTACHMENT TO LICENSE AMEN 0 MENT NO. 62 FACILITY OPERATING LICENSE NO. OPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. Tne revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages
?.-50 2-50 2-51 2-51
.yr l
l l
l l
l e
e d
+ --
4
~.
7
-. _ -. g.
j 2.0 L. 6 CCNDITICNS FOR OPIP.ATICN 2.10 Reactor Core (Continued) 2.10.2 Reactivity Centrol Systems and Core Physics ?araceters L1=its A:1:licability Applies to operatic of centrol element asse:blies and =ccitor-ing of selected core para =eters whenever the reactor is in ecid er hot shutdevn, hot standby, or power operatics conditicas.
Ob.i ective Te ensure (1) adequate shu.dev :srgin felleving a reacter trip, (2) the MTC is withis -he
-4 s of *he safety analysis, and (3) ecstrol ele =ent asse=bly operatic is withis the li=its of the setpoint and safety analysis.
Scecifiestics (1)
Shutdev Margin vith T
,,4
>21007 c,_.
Whenever the reacter is in het shutdevn, het standby or pcver operat,1c ecediticas, the shutdevr. =argin shall be 3.0% Ak/k. With the shutdev: =argi: <3.05 2/k, initiate and ccetinue bcratics until the required shutdev
.argin is achieved.
- r.a (2)
Shuticv Margin with Te31g [21W
- inenever,he reacter is is cc11 shutdev: ceniitic:s, the shuticv cargin s'-* * ' ' e > 3.G5 *%/h.
With the shutdev:
..argin <3.05 ak/k, initiate and continue beratic- --*
i the required shutdc*.. =argin is achieved.
l.
(3)
Mede$ ster '"e=ceratu e Oceff'eient S e sederater temperature coefficient (EC) shall be:
Less positive :an +0.2 x 10 h 'o /Cv 3-
'"d' g
a.
uncertainties for pcVer levels at er above 30% cf l
rated power.
l l
b.
Less positive than +0.5 x 10- ao/c? including uncertainties for pcrer levels telev 80% of rated power.
More positive than -2.3 x 10 k 40/07 including c.
uncertainties at rated pover.
Vith the moderator ta=perature ccefficient ec fir _ed outside arff cae of,the above ' *~'ts, change reac*ivity ecstrel parsmeters to bring the extrapolated M"'C value within the above ' * 'ts within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> er be is at least hot shutdeve within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
9 l
A.end=est :To. 3, 32, K3, V7, 62 2-50 l
,.,,-~e--.
.-e
,g..,,
,y-
--w-
2.0 LICUG CCND"!CNS FCR OF'P.AZION 2.10 Reactor Core (Ces:1:uedj 2.10.2 Reactivity Control Systems and Cere ?tvsies ?arameters L1=its (Conti=ued) the shutdov: sargin requirement is based upon this l'-4 ting conditic: and is ec=sistent with FSAR safety analysis asst =;-
ticus. With T cid ".210 F, the reactivity trs sie::s resulting e
frem s=y postulated accident are misinal and a 3.05 ok/k l
shu:dev: =argi provides adequate prctectien.
Cc rci Ilement Assaic11es The specifica: ices of this sectic: ensure that (1) acceptable power distributic: ' * -' t s are saist ained, ( 2 ) the -* '
t=
shutdev =argin is maintained, and (3) the potential etreets of CIA =isalig==ents are limited Oc acceptable levels.-
The statements which permit '-'ted variatices from the basic require ents are accc panied by additic:a1 restrictions which ensure that the original design criteria are met.
The specificaticus applicable to cce er scre CIA's that are deter =ined to be untrippable or stuck, and to one or =cre
=isaligned CIA's that cannot be restored to within 12 inches of any other CIA in their group, require a prc=pt shu.dev: of the reactor since any of these ec:diticus =ay be indicative of &
possible loss of =echanical functic:a1 capability of the CIA syste= and in the event of any==t91D abt.e CIA, the 1 css of shutdev =argin.
?cr s-= _isalign=ents (<15 inches absciute) cf the CIA's,
there is 1) a s-=
iegradatics in the pe*4 facters relative to these assu=ed is generating *,CO's s.:d ~ DSS set;ci :s for DN33 and linear heat rate, 2) a s_all effect c the time de-pendent ic s tern ;cver distributions rels.tive to these used in generating ICC's and LSSS set; cists for ::;3R and linear heat rate, 3) a -'" effect ce the available shutdev: =argin, s=d h ) a s-a' effect c= the ejected CIA verth used in the safe:/
analysis. S erefore, the actics stateres assceiated vith the s=all =isalig=:ent of a CIA per=its a cae hcur time 12:er-tal during which atte=;;s ay be made to restere the CIA to vithis its alig= ment require ents prior to initiati g a reductics in Che cue hour time is sufficient to 1) identi.^/ causes sever.
.cf a sisaligned CIA, 2) take appropriate corrective actic: to i
realig the CIA's, and 3)
' *-4:e the effects of xe:ce re-distribution.
Over;cver margin is provided to protect the core in the event of a large misalig:sent (>16 inches) of a CIA. Ecvever, this sis-align =e=t veuld cause distortic: of the core power distributics.
"'he reactor protective s/stes vouli not detect the degradatics is radial peaking facters and since variaticus is other s/ste=s para-
=eters (e.g., pressure and cools =0 te=;erature) ay not be sufficie A:endre=t No.
,3, 20, y, I ;, C2 2-51 f
4
., _ _ _ _ _, _, ~,..... _..,... _ _.. _.. _ _. _,. _, _ _.., _.. _,